Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

Note: This page contains sample records for the topic "test site nye" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.

Volcanic rock samples collected from the Nevada TestSite, Nye County, Nevada, between 1960 and 1985 were analyzed by thin section to obtain petrographic mode data. In order to provide rapid accessibility to the entire database, all data from the cards were entered into a computerized database. This computer format will enable workers involved in stratigraphic studies in the Nevada TestSite area and other locations in southern Nevada to perform independent analyses of the data. The data were compiled from the mode cards into two separate computer files. The first file consists of data collected from core samples taken from drill holes in the Yucca Mountain area. The second group of samples were collected from measured sections and surface mapping traverses in the Nevada TestSite area. Each data file is composed of computer printouts of tables with mode data from thin section point counts, comments on additional data, and location data. Tremendous care was taken in transferring the data from the cards to computer, in order to preserve the original information and interpretations provided by the analyzer. In addition to the data files above, a file is included that consists of Nevada TestSite petrographic data published in other US Geological Survey and Los Alamos National Laboratory reports. These data are presented to supply the user with an essentially complete modal database of samples from the volcanic stratigraphic section in the Nevada TestSite area. 18 refs., 4 figs.

The US Department of Energy (DOE) proposes to conduct a program to characterize groundwater at the Nevada TestSite (NTS), Nye County, Nevada, in accordance with a 1987 DOE memorandum stating that all past, present, and future nuclear testsites would be treated as Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites (Memorandum from Bruce Green, Weapons Design and Testing Division, June 6, 1987). DOE has prepared an environmental assessment (DOE/EA-0532) to evaluate the environmental consequences associated with the proposed action, referred to as the Groundwater Characterization Project (GCP). This proposed action includes constructing access roads and drill pads, drilling and testing wells, and monitoring these wells for the purpose of characterizing groundwater at the NTS. Long-term monitoring and possible use of these wells in support of CERCLA, as amended by the Superfund Amendments and Reauthorization Act, is also proposed. The GCP includes measures to mitigate potential impacts on sensitive biological, cultural and historical resources, and to protect workers and the environment from exposure to any radioactive or mixed waste materials that may be encountered. DOE considers those mitigation measures related to sensitive biological, cultural and historic resources as essential to render the impacts of the proposed action not significant, and DOE has prepared a Mitigation Action Plan (MAP) that explains how such mitigations will be planned and implemented. Based on the analyses presented in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, preparation of an environmental impact statement is not required and the Department is issuing this FONSI.

The Special Projects Section (SPS) of Reynolds Electrical & Engineering Co., Inc. (REECO) is responsible for characterizing the subsurface geology and hydrology of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada TestSite (NTS) for the US Department of Energy, Nevada Operations Office (DOE/NV), Environmental Restoration and Waste Management Division, Waste Operations Branch. The three Pilot Wells that comprise the Pilot Well Project are an important part of the Area 5 Site Characterization Program designed to determine the suitability of the Area 5 RWMS for disposal of low-level waste (LLW), mixed waste (MW), and transuranic waste (TRU). The primary purpose of the Pilot Well Project is two-fold: first, to characterize important water quality and hydrologic properties of the uppermost aquifer; and second, to characterize the lithologic, stratigraphic, and hydrologic conditions which influence infiltration, redistribution, and percolation, and chemical transport through the thick vadose zone in the vicinity of the Area 5 RWMS. This report describes Pilot Well drilling and coring, geophysical logging, instrumentation and stemming, laboratory testing, and in situ testing and monitoring activities.

At the request of the Department of Energy, Nevada Field Office (DOE/NV), the Desert Research Institute (DRI) conducted archaeological data recovery at drill hole U19az on the Nevada TestSite in February 1988 and April 1990. The work focused on a site that was recommended as eligible to the National Register of Historic Places. DOE/NV chose to mitigate adverse impacts to the site though a data recovery program. The mapping and collection of artifacts took place in two discrete areas, covering almost 10 hectares (24.71 acres). In addition to surface collection, 11 test pits and 12 surface scrapes were excavated. Information was sought to address four research questions concerned with the age of the site, the subsistence and demography of the site`s inhabitants, and the behavioral implications of their lithic technology. This report describes and presents the results of the data recovery at drill hole U19az. The analyses of the artifacts indicate that the site was inhabited between 5,000 years ago and historic times. Relative artifact abundance indicates the most intense use occurred from about 4,000 to 1,500 years ago.

At the request of the Department of Energy, Nevada Field Office (DOE/NV), the Desert Research Institute (DRI) conducted archaeological data recovery at drill hole U19az on the Nevada TestSite in February 1988 and April 1990. The work focused on a site that was recommended as eligible to the National Register of Historic Places. DOE/NV chose to mitigate adverse impacts to the site though a data recovery program. The mapping and collection of artifacts took place in two discrete areas, covering almost 10 hectares (24.71 acres). In addition to surface collection, 11 test pits and 12 surface scrapes were excavated. Information was sought to address four research questions concerned with the age of the site, the subsistence and demography of the site's inhabitants, and the behavioral implications of their lithic technology. This report describes and presents the results of the data recovery at drill hole U19az. The analyses of the artifacts indicate that the site was inhabited between 5,000 years ago and historic times. Relative artifact abundance indicates the most intense use occurred from about 4,000 to 1,500 years ago.

This environmental assessment (EA) examines the potential impacts to the environment from treatment of low-level radioactive liquid and low-level mixed liquid and semi-solid wastes generated at the Nevada TestSite (NTS). The potential impacts of the proposed action and alternative actions are discussed herein in accordance with the National Environmental Policy Act (NEPA) of 1969, as amended in Title 42 U.S.C. (4321), and the US Department of Energy (DOE) policies and procedures set forth in Title 10 Code of Federal Regulations (CFR) Part 1021 and DOE Order 451.1, ``NEPA Compliance Program.`` The potential environmental impacts of the proposed action, construction and operation of a centralized liquid waste treatment facility, were addressed in the Final Environmental Impact Statement for the Nevada TestSite and Off-Site Locations in the State of Nevada. However, DOE is reevaluating the need for a centralized facility and is considering other alternative treatment options. This EA retains a centralized treatment facility as the proposed action but also considers other feasible alternatives.

In 1993, Raytheon Services Nevada completed a review of natural resource literature and other sources to identify potentially exploitable resources and potential future land uses near the Area 5 Radioactive Waste Management Site (RWMS) of the Nevada TestSite (NTS), Nye County, Nevada, that could lead to future inadvertent human intrusion and subsequent release of radionuclides to the accessible environment. National Security Technologies, LLC, revised the original limited-distribution document to conform to current editorial standards and U.S. Department of Energy requirements for public release. The researchers examined the potential for future development of sand, gravel, mineral, petroleum, water resources, and rural land uses, such as agriculture, grazing, and hunting. The study was part of the performance assessment for Greater Confinement Disposal boreholes. Sand and gravel are not considered exploitable site resources because the materials are common throughout the area and the quality at the Area 5 RWMS is not ideal for typical commercial uses. Site information also indicates a very low mineral potential for the area. None of the 23 mining districts in southern Nye County report occurrences of economic mineral deposits in unconsolidated alluvium. The potential for oil and natural gas is low for southern Nye County. No occurrences of coal, tar sand, or oil shale on the NTS are reported in available literature. Several potential future uses of water were considered. Agricultural irrigation is impractical due to poor soils and existing water supply regulations. Use of water for geothermal energy development is unlikely because temperatures are too low for typical commercial applications using current technology. Human consumption of water has the most potential for cause of intrusion. The economics of future water needs may create a demand for the development of deep carbonate aquifers in the region. However, the Area 5 RWMS is not an optimal location for extraction of groundwater from the deep carbonate aquifer. Grazing and hunting are unlikely to be potential causes for inadvertent human intrusion into waste areas because of vegetation characteristics and lack of significant game animal populations.

A sequence of buried, bedded, air-fall tuffs has been used extensively as a host medium for underground nuclear tests detonated in the central part of Yucca Flat at the Nevada TestSite. Water levels within these bedded tuffs have been elevated hundreds of meters in areas where underground nuclear tests were detonated below the water table. Changes in the ground-water levels within these tuffs and changes in the rate and distribution of land-surface subsidence above these tuffs indicate that pore-fluid pressures have been slowly depressurizing since the cessation of nuclear testing in 1992. Declines in ground-water levels concurrent with regional land subsidence are explained by poroelastic deformation accompanying ground-water flow as fluids pressurized by underground nuclear detonations drain from the host tuffs into the overlying water table and underlying regional carbonate aquifer. A hydraulic conductivity of about 3 x 10-6 m/d and a specific storage of 9 x 10-6 m-1 are estimated using ground-water flow models. Cross-sectional and three-dimensional ground-water flow models were calibrated to measured water levels and to land-subsidence rates measured using Interferometric Synthetic Aperture Radar. Model results are consistent and indicate that about 2 million m3 of ground water flowed from the tuffs to the carbonate rock as a result of pressurization caused by underground nuclear testing. The annual rate of inflow into the carbonate rock averaged about 0.008 m/yr between 1962 and 2005, and declined from 0.005 m/yr in 2005 to 0.0005 m/yr by 2300.

This report summarizes the results of a Composite Analysis (CA) for the Area 5 Radioactive Waste Management Site (RWMS). The Area 5 RWMS is a US Department of Energy (DOE)-operated low-level radioactive waste (LLW) management site located in northern Frenchman Flat on the Nevada TestSite (NTS). The Area 5 RWMS has disposed of low-level radioactive waste in shallow unlined pits and trenches since 1960. Transuranic waste (TRU) and high-specific activity waste was disposed in Greater Confinement Disposal (GCD) boreholes from 1983 to 1989. The purpose of this CA is to determine if continuing operation of the Area 5 RWMS poses an acceptable or unacceptable risk to the public considering the total waste inventory and all other interacting sources of radioactive material in the vicinity. Continuing operation of the Area 5 RWMS will be considered acceptable if the total effective dose equivalent (TEDE) is less than 100 mrem in a year. If the TEDE exceeds 30 mrem in a year, a cost-benefit options analysis must be performed to determine if cost-effective management options exist to reduce the dose further. If the TEDE is found to be less than 30 mrem in a year, an analysis may be performed if warranted to determine if doses are as low as reasonably achievable (ALARA).

This report documents the analysis of data collected for ER-12-3 during the fiscal year (FY) 2005 Rainier Mesa/Shoshone Mountain well development and hydraulic testing program (herein referred to as the ''testing program''). Well ER-12-3 was constructed and tested as a part of the Corrective Action Unit (CAU) 99, Rainier Mesa/Shoshone Mountain, Phase I drilling program during FY 2005. These activities were conducted on behalf of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) for the Underground Test Area (UGTA) Project. As shown on Figure 1-1, ER-12-3 is located in central Rainier Mesa, in Area 12 of the Nevada TestSite (NTS). Figure 1-2 shows the well location in relation to the tunnels under Rainier Mesa. The well was drilled to a total depth (TD) of 4,908 feet (ft) below ground surface (bgs) (surface elevation 7,390.8 ft above mean sea level [amsl]) in the area of several tunnels mined into Rainier Mesa that were used historically for nuclear testing (NNSA/NSO, 2006). The closest nuclear test to the well location was YUBA (U-12b.10), conducted in the U-12b Tunnel approximately 1,529 ft northeast of the well site. The YUBA test working point elevation was located at approximately 6,642 ft amsl. The YUBA test had an announced yield of 3.1 kilotons (kt) (SNJV, 2006b). The purpose of this hydrogeologic investigation well is to evaluate the deep Tertiary volcanic section below the tunnel level, which is above the regional water table, and to provide information on the section of the lower carbonate aquifer-thrust plate (LCA3) located below the Tertiary volcanic section (SNJV, 2005b). Details on the drilling and completion program are presented in the ''Completion Report for Well ER-12-3 Corrective Action Unit 99: Rainier Mesa - Shoshone Mountain'' (NNSA/NSO, 2006). Development and hydraulic testing of ER-12-3 took place between June 3 and July 22, 2005. The development objectives included removing residual drilling fluids and improving the hydraulic connection of the well within the lower carbonate aquifer (LCA). The hydraulic testing objectives focused on obtaining further hydrogeologic, geochemical, and radiochemical data for the site. Details on the data collected during the testing program are presented in the report ''Rainier Mesa Well ER-12-3 Data Report for Well Development and Hydraulic Testing'' (SNJV, 2006b). Participants in ER-12-3 testing activities were: Stoller-Navarro Joint Venture (SNJV), Bechtel Nevada (BN), Desert Research Institute (DRI), Los Alamos National Laboratory (LANL), Lawrence Livermore National Laboratory (LLNL), and the U.S. Geological Survey (USGS). Stoller-Navarro Joint Venture served as the lead contractor responsible for providing site supervision, development and testing services, and waste management services; BN provided construction and engineering support services; DRI provided well logging services and participated in groundwater sampling and laboratory analyses; LANL and LLNL participated in groundwater sampling and laboratory analyses; and the USGS performed laboratory analyses. Analyses of data from the ER-12-3 testing program presented in this document were performed by SNJV except as noted.

A disposal authorization statement (DAS) was issued by the U.S. Department of Energy/Headquarters (DOE/HQ) on December 5, 2000, authorizing the DOE's National Nuclear Security Administration Nevada Operations Office to continue the operation of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada TestSite for the disposal of low-level waste and mixed low-level waste. Prior to the issuance of the DAS, the Low-Level Waste Disposal Facility Federal Review Group (LFRG) had conducted reviews of the performance assessment (PA) and the composite analysis (CA) for the Area 5 RWMS, in accordance with the requirements of the DOE Radioactive Waste Management Order DOE O 435.1. A brief history of the reviews is as follows. (The reviews were conducted by independent review teams chartered by the LFRG; the review findings and recommendations were issued in review team reports to the LFRG.) The LFRG accepted the initial PA, with conditions, on August 30, 1996. Revision 2.1 to the PA was issued in January 1998, implementing the conditions of acceptance of the 1996 PA. The LFRG reviewed Revision 2.1 as part of the Area 5 RWMS CA review during 2000, and found it acceptable. The CA and the Supplemental Information provided in response to issues identified during the initial review of the CA were accepted by the LFRG. The Supplemental Information (including the responses to four key issues) is included in the Review Team Report to the LFRG, which recommends that it be incorporated into the CA and issued to all known holders of the CA. The Area 5 RWMS DAS requires that the Supplemental Information generated during the DOE/HQ review of the CA be incorporated into the CA within one year of the date of issuance of the DAS. This report, the first addendum to the Area 5 CA, is prepared to fulfill that requirement. The Supplemental Information includes the following: Issues Identified in the Review Team Report; Crosswalk Presentation; and Maintaining Doses As Low As Reasonably Achievable. A summary of this information is included in this report, with the complete text presented in the appendices.

Between 1951 and 1992, underground nuclear weapons testing was conducted at 828 sites on the Nevada TestSite, Nye County, Nevada. Prior to and following these nuclear tests, holes were drilled and mined to collect rock samples. These samples are organized and stored by depth of borehole or drift at the U.S. Geological Survey Core Library and Data Center at Mercury, Nevada, on the Nevada TestSite. From these rock samples, rock properties were analyzed and interpreted and compiled into project files and in published reports that are maintained at the Core Library and at the U.S. Geological Survey office in Henderson, Nevada. These rock-sample data include lithologic descriptions, physical and mechanical properties, and fracture characteristics. Hydraulic properties also were compiled from holes completed in the water table. Rock samples are irreplaceable because pre-test, in-place conditions cannot be recreated and samples cannot be recollected from the many holes destroyed by testing. Documenting these data in a published report will ensure availability for future investigators.

This document is the collaborative effort of the members of an ad hoc subcommittee of the Underground Test Area (UGTA) Technical Working Group (TWG). The UGTA Project relies on data from a variety of sources; therefore, a process is needed to identify relevant factors for determining whether material-property data collected from other areas can be used to support groundwater flow, radionuclide transport, and other models within a Corrective Action Unit (CAU), and for documenting the data transfer decision and process. This document describes the overall data transfer process. Separate Parameter Descriptions will be prepared that provide information for selected specific parameters as determined by the U.S. Department of Energy (DOE) UGTA Project Manager. This document and its accompanying appendices do not provide the specific criteria to be used for transfer of data for specific uses. Rather, the criteria will be established by separate parameter-specific and model-specific Data Transfer Protocols. The CAU Data Documentation Packages and data analysis reports will apply the protocols and provide or reference a document with the data transfer evaluations and decisions.

Ground water moving through permeable Paleozoic carbonate rocks represents the most likely pathway for migration of radioactive contaminants from nuclear weapons testing at the Nevada TestSite, Nye County, Nevada. The strontium isotopic composition (87Sr/86Sr) of ground water offers a useful means of testing hydrochemical models of regional flow involving advection and reaction. However, reaction models require knowledge of 87Sr/86Sr data for carbonate rock in the Nevada TestSite vicinity, which is scarce. To fill this data gap, samples of core or cuttings were selected from 22 boreholes at depth intervals from which water samples had been obtained previously around the Nevada TestSite at Yucca Flat, Frenchman Flat, Rainier Mesa, and Mercury Valley. Dilute acid leachates of these samples were analyzed for a suite of major- and trace-element concentrations (MgO, CaO, SiO2, Al2O3, MnO, Rb, Sr, Th, and U) as well as for 87Sr/86Sr. Also presented are unpublished analyses of 114 Paleozoic carbonate samples from outcrops, road cuts, or underground sites in the Funeral Mountains, Bare Mountain, Striped Hills, Specter Range, Spring Mountains, and ranges east of the Nevada TestSite measured in the early 1990's. These data originally were collected to evaluate the potential for economic mineral deposition at the potential high-level radioactive waste repository site at Yucca Mountain and adjacent areas (Peterman and others, 1994). Samples were analyzed for a suite of trace elements (Rb, Sr, Zr, Ba, La, and Ce) in bulk-rock powders, and 87Sr/86Sr in partial digestions of carbonate rock using dilute acid or total digestions of silicate-rich rocks. Pre-Tertiary core samples from two boreholes in the central or western part of the Nevada TestSite also were analyzed. Data are presented in tables and summarized in graphs; however, no attempt is made to interpret results with respect to ground-water flow paths in this report. Present-day 87Sr/86Sr values are compared to values for Paleozoic seawater present at the time of deposition. Many of the samples have 87Sr/86Sr compositions that remain relatively unmodified from expected seawater values. However, rocks underlying the northern Nevada TestSite as well as rocks exposed at Bare Mountain commonly have elevated 87Sr/86Sr values derived from post-depositional addition of radiogenic Sr most likely from fluids circulating through rubidium-rich Paleozoic strata or Precambrian basement rocks.

This document, the Phase II Frenchman Flat transport report, presents the results of radionuclide transport simulations that incorporate groundwater radionuclide transport model statistical and structural uncertainty, and lead to forecasts of the contaminant boundary (CB) for a set of representative models from an ensemble of possible models. This work, as described in the Federal Facility Agreement and Consent Order (FFACO) Underground Test Area (UGTA) strategy (FFACO, 1996; amended 2010), forms an essential part of the technical basis for subsequent negotiation of the compliance boundary of the Frenchman Flat corrective action unit (CAU) by Nevada Division of Environmental Protection (NDEP) and National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Underground nuclear testing via deep vertical shafts was conducted at the Nevada TestSite (NTS) from 1951 until 1992. The Frenchman Flat area, the subject of this report, was used for seven years, with 10 underground nuclear tests being conducted. The U.S. Department of Energy (DOE), NNSA/NSO initiated the UGTA Project to assess and evaluate the effects of underground nuclear tests on groundwater at the NTS and vicinity through the FFACO (1996, amended 2010). The processes that will be used to complete UGTA corrective actions are described in the “Corrective Action Strategy” in the FFACO Appendix VI, Revision No. 2 (February 20, 2008).

This report presents a historical evaluation of the U12t Tunnel on the Nevada TestSite in southern Nevada. The work was conducted by the Desert Research Institute at the request of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office and the U.S. Department of Defense, Defense Threat Reduction Agency (DTRA). The U12t Tunnel is one of a series of tunnels used for underground nuclear weapons effects tests on the east side of Rainier and Aqueduct Mesas. Six nuclear weapons effects tests, Mint Leaf, Diamond Sculls, Husky Pup, Midas Myth/Milagro, Mighty Oak, and Mission Ghost, and one high explosive test, SPLAT, were conducted within the U12t Tunnel from 1970 to 1987. All six of the nuclear weapons effects tests and the high explosive test were sponsored by DTRA. Two conventional weapons experiments, Dipole Knight and Divine Eagle, were conducted in the tunnel portal area in 1997 and 1998. These experiments were sponsored by the Defense Special Weapons Agency. The U12t Tunnel complex is composed of the Portal and Mesa Areas and includes an underground tunnel with a main access drift and nine primary drifts, a substantial tailings pile fronting the tunnel portal, a series of discharge ponds downslope of the tailings pile, and two instrumentation trailer parks and 16 drill holes on top of Aqueduct Mesa. A total of 89 cultural features were recorded: 54 at the portal and 35 on the mesa. In the Portal Area, cultural features are mostly concrete pads and building foundations; other features include the portal, rail lines, the camel back, ventilation and cooling system components, communication equipment, and electrical equipment. On the mesa are drill holes, a few concrete pads, a loading ramp, and electrical equipment.

This report presents a historical evaluation of the U12t Tunnel on the Nevada TestSite in southern Nevada. The work was conducted by the Desert Research Institute at the request of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office and the U.S. Department of Defense, Defense Threat Reduction Agency (DTRA). The U12t Tunnel is one of a series of tunnels used for underground nuclear weapons effects tests on the east side of Rainier and Aqueduct Mesas. Six nuclear weapons effects tests, Mint Leaf, Diamond Sculls, Husky Pup, Midas Myth/Milagro, Mighty Oak, and Mission Ghost, and one high explosive test, SPLAT, were conducted within the U12t Tunnel from 1970 to 1987. All six of the nuclear weapons effects tests and the high explosive test were sponsored by DTRA. Two conventional weapons experiments, Dipole Knight and Divine Eagle, were conducted in the tunnel portal area in 1997 and 1998. These experiments were sponsored by the Defense Special Weapons Agency. The U12t Tunnel complex is composed of the Portal and Mesa Areas and includes an underground tunnel with a main access drift and nine primary drifts, a substantial tailings pile fronting the tunnel portal, a series of discharge ponds downslope of the tailings pile, and two instrumentation trailer parks and 16 drill holes on top of Aqueduct Mesa. A total of 89 cultural features were recorded: 54 at the portal and 35 on the mesa. In the Portal Area, cultural features are mostly concrete pads and building foundations; other features include the portal, rail lines, the camel back, ventilation and cooling system components, communication equipment, and electrical equipment. On the mesa are drill holes, a few concrete pads, a loading ramp, and electrical equipment.

This report presents a historical evaluation of the U12t Tunnel on the Nevada TestSite in southern Nevada. The work was conducted by the Desert Research Institute at the request of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office and the U.S. Department of Defense, Defense Threat Reduction Agency (DTRA). The U12t Tunnel is one of a series of tunnels used for underground nuclear weapons effects tests on the east side of Rainier and Aqueduct Mesas. Six nuclear weapons effects tests, Mint Leaf, Diamond Sculls, Husky Pup, Midas Myth/Milagro, Mighty Oak, and Mission Ghost, and one high explosive test, SPLAT, were conducted within the U12t Tunnel from 1970 to 1987. All six of the nuclear weapons effects tests and the high explosive test were sponsored by DTRA. Two conventional weapons experiments, Dipole Knight and Divine Eagle, were conducted in the tunnel portal area in 1997 and 1998. These experiments were sponsored by the Defense Special Weapons Agency. The U12t Tunnel complex is composed of the Portal and Mesa Areas and includes an underground tunnel with a main access drift and nine primary drifts, a substantial tailings pile fronting the tunnel portal, a series of discharge ponds downslope of the tailings pile, and two instrumentation trailer parks and 16 drill holes on top of Aqueduct Mesa. A total of 89 cultural features were recorded: 54 at the portal and 35 on the mesa. In the Portal Area, cultural features are mostly concrete pads and building foundations; other features include the portal, rail lines, the camel back, ventilation and cooling system components, communication equipment, and electrical equipment. On the mesa are drill holes, a few concrete pads, a loading ramp, and electrical equipment.

Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

Note: This page contains sample records for the topic "test site nye" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.

This report presents a historical evaluation of the U12t Tunnel on the Nevada TestSite in southern Nevada. The work was conducted by the Desert Research Institute at the request of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office and the U.S. Department of Defense, Defense Threat Reduction Agency (DTRA). The U12t Tunnel is one of a series of tunnels used for underground nuclear weapons effects tests on the east side of Rainier and Aqueduct Mesas. Six nuclear weapons effects tests, Mint Leaf, Diamond Sculls, Husky Pup, Midas Myth/Milagro, Mighty Oak, and Mission Ghost, and one high explosive test, SPLAT, were conducted within the U12t Tunnel from 1970 to 1987. All six of the nuclear weapons effects tests and the high explosive test were sponsored by DTRA. Two conventional weapons experiments, Dipole Knight and Divine Eagle, were conducted in the tunnel portal area in 1997 and 1998. These experiments were sponsored by the Defense Special Weapons Agency. The U12t Tunnel complex is composed of the Portal and Mesa Areas and includes an underground tunnel with a main access drift and nine primary drifts, a substantial tailings pile fronting the tunnel portal, a series of discharge ponds downslope of the tailings pile, and two instrumentation trailer parks and 16 drill holes on top of Aqueduct Mesa. A total of 89 cultural features were recorded: 54 at the portal and 35 on the mesa. In the Portal Area, cultural features are mostly concrete pads and building foundations; other features include the portal, rail lines, the camel back, ventilation and cooling system components, communication equipment, and electrical equipment. On the mesa are drill holes, a few concrete pads, a loading ramp, and electrical equipment.

This report presents a historical evaluation of the U12t Tunnel on the Nevada TestSite in southern Nevada. The work was conducted by the Desert Research Institute at the request of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office and the U.S. Department of Defense, Defense Threat Reduction Agency (DTRA). The U12t Tunnel is one of a series of tunnels used for underground nuclear weapons effects tests on the east side of Rainier and Aqueduct Mesas. Six nuclear weapons effects tests, Mint Leaf, Diamond Sculls, Husky Pup, Midas Myth/Milagro, Mighty Oak, and Mission Ghost, and one high explosive test, SPLAT, were conducted within the U12t Tunnel from 1970 to 1987. All six of the nuclear weapons effects tests and the high explosive test were sponsored by DTRA. Two conventional weapons experiments, Dipole Knight and Divine Eagle, were conducted in the tunnel portal area in 1997 and 1998. These experiments were sponsored by the Defense Special Weapons Agency. The U12t Tunnel complex is composed of the Portal and Mesa Areas and includes an underground tunnel with a main access drift and nine primary drifts, a substantial tailings pile fronting the tunnel portal, a series of discharge ponds downslope of the tailings pile, and two instrumentation trailer parks and 16 drill holes on top of Aqueduct Mesa. A total of 89 cultural features were recorded: 54 at the portal and 35 on the mesa. In the Portal Area, cultural features are mostly concrete pads and building foundations; other features include the portal, rail lines, the camel back, ventilation and cooling system components, communication equipment, and electrical equipment. On the mesa are drill holes, a few concrete pads, a loading ramp, and electrical equipment.

This report presents a historical evaluation of the U12t Tunnel on the Nevada TestSite in southern Nevada. The work was conducted by the Desert Research Institute at the request of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office and the U.S. Department of Defense, Defense Threat Reduction Agency (DTRA). The U12t Tunnel is one of a series of tunnels used for underground nuclear weapons effects tests on the east side of Rainier and Aqueduct Mesas. Six nuclear weapons effects tests, Mint Leaf, Diamond Sculls, Husky Pup, Midas Myth/Milagro, Mighty Oak, and Mission Ghost, and one high explosive test, SPLAT, were conducted within the U12t Tunnel from 1970 to 1987. All six of the nuclear weapons effects tests and the high explosive test were sponsored by DTRA. Two conventional weapons experiments, Dipole Knight and Divine Eagle, were conducted in the tunnel portal area in 1997 and 1998. These experiments were sponsored by the Defense Special Weapons Agency. The U12t Tunnel complex is composed of the Portal and Mesa Areas and includes an underground tunnel with a main access drift and nine primary drifts, a substantial tailings pile fronting the tunnel portal, a series of discharge ponds downslope of the tailings pile, and two instrumentation trailer parks and 16 drill holes on top of Aqueduct Mesa. A total of 89 cultural features were recorded: 54 at the portal and 35 on the mesa. In the Portal Area, cultural features are mostly concrete pads and building foundations; other features include the portal, rail lines, the camel back, ventilation and cooling system components, communication equipment, and electrical equipment. On the mesa are drill holes, a few concrete pads, a loading ramp, and electrical equipment.

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) initiated the Underground Test Area (UGTA) Subproject to assess and evaluate radiologic groundwater contamination resulting from underground nuclear testing at the NTS. These activities are overseen by the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended March 2010). For Frenchman Flat, the UGTA Subproject addresses media contaminated by the underground nuclear tests, which is limited to geologic formations within the saturated zone or 100 meters (m) or less above the water table. Transport in groundwater is judged to be the primary mechanism of migration for the subsurface contamination away from the Frenchman Flat underground nuclear tests. The intent of the UGTA Subproject is to assess the risk to the public from the groundwater contamination produced as a result of nuclear testing. The primary method used to assess this risk is the development of models of flow and contaminant transport to forecast the extent of potentially contaminated groundwater for the next 1,000 years, establish restrictions to groundwater usage, and implement a monitoring program to verify protectiveness. For the UGTA Subproject, contaminated groundwater is that which exceeds the radiological standards of the Safe Drinking Water Act (CFR, 2009) the State of Nevada’s groundwater quality standard to protect human health and the environment. Contaminant forecasts are expected to be uncertain, and groundwater monitoring will be used in combination with land-use control to build confidence in model results and reduce risk to the public. Modeling forecasts of contaminant transport will provide the basis for negotiating a compliance boundary for the Frenchman Flat Corrective Action Unit (CAU). This compliance boundary represents a regulatory-based distinction between groundwater contaminated or not contaminated by underground testing. Transport modeling simulations are used to compute radionuclide concentrations in time and space within the CAU for the 1,000-year contaminant boundary. These three-dimensional (3-D) concentration simulations are integrated into probabilistic forecasts of the likelihood of groundwater exceeding or remaining below the radiological standards of the Safe Drinking Water Act (CFR, 2009) defined as the contaminant boundary. Contaminant boundaries are not discrete predictions of the location or concentration of contaminants, but instead are spatial representations of the probability of exceeding Safe Drinking Water Act radiological standards. The forecasts provide planning tools to facilitate regulatory decisions designed to protect the health and safety of the public.

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada TestSite (Bechtel Nevada, 2000) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs) for each of the facilities, and reports the results in an annual summary report to the U.S. Department of Energy Headquarters. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (U.S. Department of Energy [DOE]). The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office performed annual reviews in fiscal year (FY) 2004 by evaluating operational factors and research results that impact the continuing validity of the PA and CA results. This annual summary report presents data and conclusions from the FY 2004 review, and determines the adequacy of the PAs and CAs. Operational factors, such as the waste form and containers, facility design, waste receipts, closure plans, as well as monitoring results and research and development (R&D) activities were reviewed in FY 2004 for the determination of the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada TestSite relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed for the determination of the adequacy of the CAs.

This report documents the analysis of data collected for Well ER-6-2 during fiscal year (FY) 2004 Yucca Flat well development and testing program (herein referred to as the ''testing program''). Participants in Well ER-6-2 field development and hydraulic testing activities were: Stoller-Navarro Joint Venture (SNJV), Bechtel Nevada (BN), Desert Research Institute (DRI), Los Alamos National Laboratory (LANL), Lawrence Livermore National Laboratory (LLNL), U.S. Geological Survey (USGS), and the University of Nevada, Las Vegas-Harry Reid Center (UNLV-HRC). The analyses of data collected from the Well ER-6-2 testing program were performed by the SNJV.

This report documents the analysis of data collected for ER-12-4 during the fiscal year (FY) 2005 Rainier Mesa/Shoshone Mountain well development and hydraulic testing program (herein referred to as the ''testing program'') and hydraulic response data from the FY 2006 Sampling Program. Well ER-12-4 was constructed and tested as a part of the Corrective Action Unit (CAU) 99, Rainier Mesa/Shoshone Mountain, Phase I drilling program during FY 2005. These activities were conducted on behalf of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) for the Underground Test Area (UGTA) Subproject. As shown on Figure 1-1, ER-12-4 is located in central Rainier Mesa, in Area 12 of the Nevada TestSite (NTS). Figure 1-2 shows the well location in relation to the tunnels under Rainier Mesa. The well was drilled to a total depth (TD) of 3,715 feet (ft) below ground surface (bgs) (surface elevation 6,883.7 ft above mean sea level [amsl]) in the area of several tunnels mined into Rainier Mesa that were used historically for nuclear testing (NNSA/NSO, 2006). The closest nuclear test to the well location was MIGHTY OAK (U-12t.08), conducted in the U-12t Tunnel approximately 475 ft north of the well site. The MIGHTY OAK test working point elevation was located at approximately 5,620 ft amsl. The MIGHTY OAK test had an announced yield of ''less than 20 kilotons'' (DOE/NV, 2000). The purpose of this hydrogeologic investigation well is to evaluate the deep Tertiary volcanic section below the tunnel level, which is above the regional water table, and to provide information on the section of the lower carbonate aquifer - thrust plate (LCA3), located below the Tertiary volcanic section (SNJV, 2005b). Details on the drilling and completion program are presented in the ''Completion Report for Well ER-12-4 Corrective Action Unit 99: Rainier Mesa-Shoshone Mountain'' (NNSA/NSO, 2006). Participants in ER-12-4 testing activities were: Stoller-Navarro Joint Venture (SNJV), Bechtel Nevada (BN), Desert Research Institute (DRI), Los Alamos National Laboratory (LANL), Lawrence Livermore National Laboratory (LLNL), and the U.S. Geological Survey (USGS). Stoller-Navarro Joint Venture served as the lead contractor responsible for providing site supervision, development and testing services, and waste management services; BN provided construction and engineering support services; DRI provided well logging services and participated in groundwater sampling and laboratory analyses; LANL and LLNL participated in groundwater sampling and laboratory analyses; and the USGS performed laboratory analyses. Analyses of data from the ER-12-4 testing program presented in this document were performed by SNJV except as noted. These same contractors participated in the FY 2006 Sampling Program.

This Special Analysis (SA) was prepared to assess the potential impact of inadvertent disposal of a limited quantity of transuranic (TRU) waste in classified Trench 4 (T04C) within the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada TestSite (NTS). The Area 5 RWMS is a low-level radioactive waste disposal site in northern Frenchman Flat on the Nevada TestSite (NTS). The Area 5 RWMS is regulated by the U.S. Department of Energy (DOE) under DOE Order 435.1 and DOE Manual (DOE M) 435.1-1. The primary objective of the SA is to evaluate if inadvertent disposal of limited quantities of TRU waste in a shallow land burial trench at the Area 5 RWMS is in compliance with the existing, approved Disposal Authorization Statement (DAS) issued under DOE M 435.1-1. In addition, supplemental analyses are performed to determine if there is reasonable assurance that the requirements of Title 40, Code of Federal Regulations (CFR), Part 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes, can be met. The 40 CFR 191 analyses provide supplemental information regarding the risk to human health and the environment of leaving the TRU waste in T04C. In 1989, waste management personnel reviewing classified materials records discovered that classified materials buried in trench T04C at the Area 5 RWMS contained TRU waste. Subsequent investigations determined that a total of 102 55-gallon drums of TRU waste from Rocky Flats were buried in trench T04C in 1986. The disposal was inadvertent because unclassified records accompanying the shipment indicated that the waste was low-level. The exact location of the TRU waste in T04C was not recorded and is currently unknown. Under DOE M 435.1-1, Chapter IV, Section P.5, low-level waste disposal facilities must obtain a DAS. The DAS specifies conditions that must be met to operate within the radioactive waste management basis, consisting of a performance assessment (PA), composite analysis (CA), closure plan, monitoring plan, waste acceptance criteria, and a PA/CA maintenance plan. The DOE issued a DAS for the Area 5 RWMS in 2000. The Area 5 RWMS DAS was, in part, based on review of a CA as required under DOE M 435.1-1, Chapter IV, Section P.(3). A CA is a radiological assessment required for DOE waste disposed before 26 September 1988 and includes the radiological dose from all sources of radioactive material interacting with all radioactive waste disposed at the Area 5 RWMS. The approved Area 5 RWMS CA, which includes the inventory of TRU waste in T04C, indicates that the Area 5 RWMS waste inventory and all interacting sources of radioactive material can meet the 0.3 mSv dose constraint. The composite analysis maximum annual dose for a future resident at the Area 5 RWMS was estimated to be 0.01 mSv at 1,000 years. Therefore, the inadvertent disposal of TRU in T04C is protective of the public and the environment, and compliant with all the applicable requirements in DOE M 435.1-1 and the DAS. The U.S. Environmental Protection Agency promulgated 40 CFR 191 to establish standards for the planned disposal of spent nuclear fuel, high level, and transuranic wastes in geologic repositories. Although not required, the National Nuclear Security Administration Nevada Site Office requested a supplemental analysis to evaluate the likelihood that the inadvertent disposal of TRU waste in T04C meets the requirements of 40 CFR 191. The SA evaluates the likelihood of meeting the 40 CFR 191 containment requirements (CRs), assurance requirements, individual protection requirements (IPRs), and groundwater protection standards. The results of the SA indicate that there is a reasonable expectation of meeting all the requirements of 40 CFR 191. The conclusion of the SA is that the Area 5 RWMS with the TRU waste buried in T04C is in compliance with all requirements in DOE M 435.1-1 and the DAS. Compliance with the DAS is demonstrated by the results of the Area 5 RWMS CA. Supplemental analyses in the SA indicate there is a

The Nevada TestSite (NTS) was established in 1951 as a proving ground for nuclear weapons. The site had formerly been part of an Air Force bombing and gunnery range during World War II. Sponsor-directed studies of the geology, hydrogeology, and hydrology of the NTS began about 1956 and were broad based in nature, but were related mainly to the effects of the detonation of nuclear weapons. These effects included recommending acceptable media and areas for underground tests, the possibility of off-site contamination of groundwater, air blast and surface contamination in the event of venting, ground-shock damage that could result from underground blasts, and studies in support of drilling and emplacement. The studies were both of a pure scientific nature and of a practical applied nature. The NTS was the site of 828 underground nuclear tests and 100 above-ground tests conducted between 1951 and 1992 (U.S. Department of Energy, 1994a). After July 1962, all nuclear tests conducted in the United States were underground, most of them at the NTS. The first contained underground nuclear explosion was detonated on September 19, 1957, following extensive study of the underground effect of chemical explosives. The tests were performed by U.S. Department of Energy (DOE) and its predecessors, the U.S. Atomic Energy Commission and the Energy Research and Development Administration. As part of a nationwide complex for nuclear weapons design, testing and manufacturing, the NTS was the location for continental testing of new and stockpiled nuclear devices. Other tests, including Project {open_quotes}Plowshare{close_quotes} experiments to test the peaceful application of nuclear explosives, were conducted on several parts of the site. In addition, the Defense Nuclear Agency tested the effect of nuclear detonations on military hardware.

Almost 4,000 water-level measurements in 216 wells in the Yucca Flat area from 1951 to 2003 were quality assured and analyzed. An interpretative database was developed that describes water-level conditions for each water level measured in Yucca Flat. Multiple attributes were assigned to each water-level measurement in the database to describe the hydrologic conditions at the time of measurement. General quality, temporal variability, regional significance, and hydrologic conditions are attributed for each water-level measurement. The database also includes narratives that discuss the water-level history of each well. Water levels in 34 wells were analyzed for variability and for statistically significant trends. An attempt was made to identify the cause of many of the water-level fluctuations or trends. Potential causes include equilibration following well construction or development, pumping in the monitoring well, withdrawals from a nearby supply well, recharge from precipitation, earthquakes, underground nuclear tests, land subsidence, barometric pressure, and Earth tides. Some of the naturally occurring fluctuations in water levels may result from variations in recharge. The magnitude of the overall water-level change for these fluctuations generally is less than 2 feet. Long-term steady-state hydrographs for most of the wells open to carbonate rock have a very similar pattern. Carbonate-rock wells without the characteristic pattern are directly west of the Yucca and Topgallant faults in the southwestern part of Yucca Flat. Long-term steady-state hydrographs from wells open to volcanic tuffs or the Eleana confining unit have a distinctly different pattern from the general water-level pattern of the carbonate-rock aquifers. Anthropogenic water-level fluctuations were caused primarily by water withdrawals and nuclear testing. Nuclear tests affected water levels in many wells. Trends in these wells are attributed to test-cavity infilling or the effects of depressurization following nuclear testing. The magnitude of the overall water-level change for wells with anthropogenic trends can be large, ranging from several feet to hundreds of feet. Vertical water-level differences at 27 sites in Yucca Flat with multiple open intervals were compared. Large vertical differences were noted in volcanic rocks and in boreholes where water levels were affected by nuclear tests. Small vertical differences were noted within the carbonate-rock and valley-fill aquifers. Vertical hydraulic gradients generally are downward in volcanic rocks and from pre-Tertiary clastic rocks toward volcanic- or carbonate-rock units.

Contaminants introduced into the subsurface of the Nevada TestSite at Rainier Mesa and Shoshone Mountain by underground nuclear testing are of concern to the U.S. Department of Energy and regulators responsible for protecting human health and safety. Although contaminants were introduced into low-permeability rocks above the regional flow system, the potential for contaminant movement away from the underground test areas and into the accessible environment is greatest by ground-water transport. The primary hydrologic control on this transport is evaluated and examined through a series of contour maps developed to represent the water-level distribution within each of the major aquifers underlying the area. Aquifers were identified and their extents delineated by merging and analyzing multiple hydrostratigraphic framework models developed by other investigators from existing geologic information. The contoured water-level distribution in each major aquifer was developed from a detailed evaluation and assessment of available water-level measurements. Multiple spreadsheets that accompany this report provide pertinent water-level and geologic data by well or drill hole. Aquifers are mapped, presented, and discussed in general terms as being one of three aquifer types—volcanic aquifer, upper carbonate aquifer, or lower carbonate aquifer. Each of these aquifer types was subdivided and mapped as independent continuous and isolated aquifers, based on the continuity of its component rock. Ground-water flow directions, as related to the transport of test-generated contaminants, were developed from water-level contours and are presented and discussed for each of the continuous aquifers. Contoured water-level altitudes vary across the study area and range from more than 5,000 feet in the volcanic aquifer beneath a recharge area in the northern part of the study area to less than 2,450 feet in the lower carbonate aquifer in the southern part of the study area. Variations in water-level altitudes within any single continuous aquifer range from a few hundred feet in a lower carbonate aquifer to just more than 1,100 feet in a volcanic aquifer. Flow directions throughout the study area are dominantly southward with minor eastward or westward deviations. Primary exceptions are westward flow in the northern part of the volcanic aquifer and eastward flow in the eastern part of the lower carbonate aquifer. Northward flow in the upper and lower carbonate aquifers in the northern part of the study area is possible but cannot be substantiated because data are lacking. Interflow between continuous aquifers is evaluated and mapped to define major flow paths. These flow paths delineate tributary flow systems, which converge to form the regional ground-water flow system. The implications of these tributary flow paths in controlling transport away from the underground test areas at Rainier Mesa and Shoshone Mountain are discussed. The obvious data gaps contributing to uncertainties in the delineation of aquifers and development of water-level contours are identified and evaluated.

Underground Test Area (UGTA) corrective action unit (CAU) groundwater flow and contaminant transport models of the Nevada TestSite (NTS) and vicinity are built upon hydrostratigraphic framework models (HFMs) that utilize the hydrostratigraphic unit (HSU) as the fundamental modeling component. The delineation and three-dimensional (3-D) modeling of HSUs within the highly complex geologic terrain that is the NTS requires a hydrostratigraphic system that is internally consistent, yet flexible enough to account for overlapping model areas, varied geologic terrain, and the development of multiple alternative HFMs. The UGTA CAU-scale hydrostratigraphic system builds on more than 50 years of geologic and hydrologic work in the NTS region. It includes 76 HSUs developed from nearly 300 stratigraphic units that span more than 570 million years of geologic time, and includes rock units as diverse as marine carbonate and siliciclastic rocks, granitic intrusives, rhyolitic lavas and ash-flow tuffs, and alluvial valley-fill deposits. The UGTA CAU-scale hydrostratigraphic system uses a geology-based approach and two-level classification scheme. The first, or lowest, level of the hydrostratigraphic system is the hydrogeologic unit (HGU). Rocks in a model area are first classified as one of ten HGUs based on the rock’s ability to transmit groundwater (i.e., nature of their porosity and permeability), which at the NTS is mainly a function of the rock’s primary lithology, type and degree of postdepositional alteration, and propensity to fracture. The second, or highest, level within the UGTA CAU-scale hydrostratigraphic system is the HSU, which is the fundamental mapping/modeling unit within UGTA CAU-scale HFMs. HSUs are 3-D bodies that are represented in the finite element mesh for the UGTA groundwater modeling process. HSUs are defined systematically by stratigraphically organizing HGUs of similar character into larger HSUs designations. The careful integration of stratigraphic information in the development of HSUs is important to assure individual HSUs are internally consistent, correlatable, and mappable throughout all the model areas.

In 1991 the Quaternary Sciences Center at the Desert Research Institute (DRI) conducted archaeological investigations at sample unit U19adPL on Pahute Mesa at the request of the Department of Energy, Nevada Field Office. This work was conducted under the Long Range Study Plan, a data recovery program designed to intensively study an 11 percent geographic sample of the cultural resources on Pahute and Rainier mesas. The focus of the research was site 26NY3393. This site consists of a gabled wooden lodge with a hearth, a rock ring, and a dim use artifacts scatter of ceramics, lithic tools, and lithic debitage. The structure is the only gabled log structure known on Pahute and Rainier mesas, and associated artifacts included shell and glass beads. Based on temporally diagnostic artifacts, the occupation of site 26NY3393 spans 8000 years. There is no evidence that the site was occupied continuously for any great length of time. It is more likely that Native Americans inhabited the area intermittently on a seasonal basis. The gabled wooden lodge is a late construction, probably dating between A.D. 1760 and 1865. This report documents and presents the results of the archaeological work at sample unit U19adPL.

Wells ER-20-4 and ER-20-8 were drilled during fiscal year (FY) 2009 and FY 2010 (NNSA/NSO, 2011a and b). The closest underground nuclear test detonations to the area of investigation are TYBO (U-20y), BELMONT (U-20as), MOLBO (U-20ag), BENHAM (U-20c), and HOYA (U-20 be) (Figure 1-1). The TYBO, MOLBO, and BENHAM detonations had working points located below the regional water table. The BELMONT and HOYA detonation working points were located just above the water table, and the cavity for these detonations are calculated to extend below the water table (Pawloski et al., 2002). The broad purpose of Wells ER-20-4 and ER-20-8 is to determine the extent of radionuclide-contaminated groundwater, the geologic formations, groundwater geochemistry as an indicator of age and origin, and the water-bearing properties and hydraulic conditions that influence radionuclide migration. Well development and testing is performed to determine the hydraulic properties at the well and between other wells, and to obtain groundwater samples at the well that are representative of the formation at the well. The area location, wells, underground nuclear detonations, and other features are shown in Figure 1-1. Hydrostratigraphic cross sections A-A’, B-B’, C-C’, and D-D’ are shown in Figures 1-2 through 1-5, respectively.

The Phase II Frenchman Flat groundwater flow model is a key element in the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) corrective action strategy for the Underground Test Area (UGTA) Frenchman Flat corrective action unit (CAU). The objective of this integrated process is to provide an estimate of the vertical and horizontal extent of contaminant migration for each CAU to predict contaminant boundaries. A contaminant boundary is the model-predicted perimeter that defines the extent of radionuclide-contaminated groundwater from underground testing above background conditions exceeding the ''Safe Drinking Water Act'' (SDWA) standards. The contaminant boundary will be composed of both a perimeter boundary and a lower hydrostratigraphic unit (HSU) boundary. The computer model will predict the location of this boundary within 1,000 years and must do so at a 95 percent level of confidence. Additional results showing contaminant concentrations and the location of the contaminant boundary at selected times will also be presented. These times may include the verification period, the end of the five-year proof-of-concept period, as well as other times that are of specific interest. This report documents the development and implementation of the groundwater flow model for the Frenchman Flat CAU. Specific objectives of the Phase II Frenchman Flat flow model are to: (1) Incorporate pertinent information and lessons learned from the Phase I Frenchman Flat CAU models. (2) Develop a three-dimensional (3-D), mathematical flow model that incorporates the important physical features of the flow system and honors CAU-specific data and information. (3) Simulate the steady-state groundwater flow system to determine the direction and magnitude of groundwater fluxes based on calibration to Frenchman Flat hydrogeologic data. (4) Quantify the uncertainty in the direction and magnitude of groundwater flow due to uncertainty in parameter values and alternative component conceptual models (e.g., geology, boundary flux, and recharge).

This report documents the interpretation and analysis of the hydraulic data collected for the Fiscal Year (FY) 2004 Multiple-Well Aquifer Test-Tracer Test (MWAT-TT) conducted at the ER-6-1 Well Cluster in Yucca Flat Corrective Action Unit (CAU) 97, on the Nevada TestSite (NTS). The MWAT-TT was performed to investigate CAU-scale groundwater flow and transport processes related to the transport of radionuclides from sources on the NTS through the Lower Carbonate Aquifer (LCA) Hydrostratigraphic Unit (HSU). The ER-6-1 MWAT-TT was planned and executed by contractor participants for the Underground Test Area (UGTA) Project of the Environmental Restoration (ER) program of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Participants included Stoller-Navarro Joint Venture (SNJV), the Environmental Engineering Services Contractor; Bechtel Nevada (BN); the Desert Research Institute (DRI); Los Alamos National Laboratory; and the University of Nevada, Las Vegas-Harry Reid Center. The SNJV team consists of the S.M. Stoller Corporation, Navarro Research and Engineering, Battelle Memorial Institute, INTERA Inc., and Weston Solutions, Inc. The MWAT-TT was implemented according to the ''Underground Test Area Project, ER-6-1 Multi-Well Aquifer Test - Tracer Test Plan'' (SNJV, 2004a) issued in April 2004. The objective of the aquifer test was to determine flow processes and local hydraulic properties for the LCA through long-term constant-rate pumping at the well cluster. This objective was to be achieved in conjunction with detailed sampling of the composite tracer breakthrough at the pumping well, as well as with depth-specific sampling and logging at multiple wells, to provide information for the depth-discrete analysis of formation hydraulic properties, particularly with regard to fracture properties.

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada TestSite requires an annual review to assess the adequacy of the Performance Assessments (PAs) and Composite Analyses (CAs) for each of the facilities, with the results submitted annually to U.S. Department of Energy (DOE) Headquarters. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan. The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) performed an annual review in fiscal year (FY) 2008 by evaluating operational factors and research results that impact the continuing validity of the PAs and CAs. This annual summary report presents data and conclusions from the FY 2008 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada TestSite relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs.

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 Radioactive Wate Management Site (RWMS) Performance Assessments (PAs) and Composite Analyses (CAs) in fiscal year (FY) 2009. This annual summary report presents data and conclusions from the FY 2009 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada TestSite relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs.

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) initiated the Underground Test Area (UGTA) Project to assess and evaluate the effects of the underground nuclear weapons tests on groundwater beneath the Nevada TestSite (NTS) and vicinity. The framework for this evaluation is provided in Appendix VI, Revision No. 1 (December 7, 2000) of the Federal Facility Agreement and Consent Order (FFACO, 1996). Section 3.0 of Appendix VI ''Corrective Action Strategy'' of the FFACO describes the process that will be used to complete corrective actions specifically for the UGTA Project. The objective of the UGTA corrective action strategy is to define contaminant boundaries for each UGTA corrective action unit (CAU) where groundwater may have become contaminated from the underground nuclear weapons tests. The contaminant boundaries are determined based on modeling of groundwater flow and contaminant transport. A summary of the FFACO corrective action process and the UGTA corrective action strategy is provided in Section 1.5. The FFACO (1996) corrective action process for the Yucca Flat/Climax Mine CAU 97 was initiated with the Corrective Action Investigation Plan (CAIP) (DOE/NV, 2000a). The CAIP included a review of existing data on the CAU and proposed a set of data collection activities to collect additional characterization data. These recommendations were based on a value of information analysis (VOIA) (IT, 1999), which evaluated the value of different possible data collection activities, with respect to reduction in uncertainty of the contaminant boundary, through simplified transport modeling. The Yucca Flat/Climax Mine CAIP identifies a three-step model development process to evaluate the impact of underground nuclear testing on groundwater to determine a contaminant boundary (DOE/NV, 2000a). The three steps are as follows: (1) Data compilation and analysis that provides the necessary modeling data that is completed in two parts: the first addressing the groundwater flow model, and the second the transport model. (2) Development of a groundwater flow model. (3) Development of a groundwater transport model. This report presents the results of the first part of the first step, documenting the data compilation, evaluation, and analysis for the groundwater flow model. The second part, documentation of transport model data will be the subject of a separate report. The purpose of this document is to present the compilation and evaluation of the available hydrologic data and information relevant to the development of the Yucca Flat/Climax Mine CAU groundwater flow model, which is a fundamental tool in the prediction of the extent of contaminant migration. Where appropriate, data and information documented elsewhere are summarized with reference to the complete documentation. The specific task objectives for hydrologic data documentation are as follows: (1) Identify and compile available hydrologic data and supporting information required to develop and validate the groundwater flow model for the Yucca Flat/Climax Mine CAU. (2) Assess the quality of the data and associated documentation, and assign qualifiers to denote levels of quality. (3) Analyze the data to derive expected values or spatial distributions and estimates of the associated uncertainty and variability.

The Yucca Mountain Site Characterization office has established an environmental program to ensure that facilities are operated in order to protect, maintain, and restore environmental quality, minimize potential threats to the environment and the public, and comply with environmental policies and US DOE orders. The status of the environmental program has been summarized in this annual report to characterize performance, confirm compliance with environmental requirements, and highlight significant programs and efforts during CY 1994. Monitoring, archaeology, groundwater, ecosystems, tortoise conservation, waste minimization, etc., are covered.

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Test hole USW UZ-6, located 1.8 kilometers west of the Nevada TestSite on a major north-trending ridge at Yucca Mountain, was dry drilled in Tertiary tuff to a depth of 575 meters. The area near this site is being considered by the US Department of Energy for potential construction of a high-level, radioactive-waste repository. Test hole USW UZ-6 is one of seven test holes completed in the unsaturated zone as part of the US Geological Survey`s Yucca Mountain Project to characterize the potential repository site. Data pertaining to borehole drilling and construction, lithology of geologic units penetrated, and laboratory analyses for hydrologic characteristics of samples of drill-bit cuttings are included in this report.

This report describes the methods and results of a special analysis (SA) of the Area 3 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The purpose of the SA is to determine if the approved performance assessment (PA) and composite analysis (CA) (Shott et al., 2001) remain valid. The Area 3 RWMS PA and CA were prepared as a single document and received conditional approval on October 6, 1999. A conditional Disposal Authorization Statement (DAS) for the Area 3 RWMS was issued on October 20, 1999. Since preparation of the approved PA and CA, new information and additional environmental monitoring data have been used to update the PA and CA. At the same time, continual advancements in computer processors and software have allowed improvement to the PA and CA models. Annual reviews of the PA and CA required by U.S. Department of Energy (DOE) Order DOE O 435.1 have documented multiple changes occurring since preparation of the PA and CA. Potentially important changes include: Development of a new and improved baseline PA and CA model implemented in the probabilistic GoldSim simulation platform. A significant increase in the waste inventory disposed at the site. Revision and updating of model parameters based on additional years of site monitoring data and new research and development results. Although changes have occurred, many important PA/CA issues remain unchanged, including the site conceptual model, important features, events, and processes, and the points of compliance. The SA is performed to document the current status of the PA/CA model and to quantitatively assess the impact of cumulative changes on the PA and CA results. The results of the SA are used to assess the validity of the approved PA/CA and make a determination if revision of the PA or CA is necessary. The SA was performed using the Area 3 RWMS, version 2.102, GoldSim model, the current baseline PA/CA model. Comparison of the maximum SA results with the PA performance objectives indicates that there continues to be a reasonable expectation of compliance. The resident exposure scenario was evaluated for compliance with the air pathway and all-pathways annual total effective dose (TED) performance objectives. The maximum mean air pathway TED, 7E-6 millisievert (mSv) at 1,000 years (y) has decreased relative to the approved PA and is significantly less than the 0.1 mSv limit. The maximum mean all-pathways annual TED, 7E-5 mSv at 1,000 y has increased but remains a small fraction of the 0.25 mSv limit. The SA maximum mean radon-222 (222Rn) flux density, 0.03 becquerel per square meter per second (Bq m-2 s-1), has increased relative to the PA results but is significantly less than the 0.74 Bq m-2 s-1 limit. The SA results continue to support a conclusion that the disposed waste inventory is protective of intruders and groundwater resources. The maximum mean intruder TED, 0.01 mSv for an acute construction scenario at the U-3ah/at disposal unit, was less than the 5 mSv performance measure. Site monitoring data and research results continue to support a conclusion that a groundwater pathway will not exist within the 1,000 y compliance period. Projected releases to the environment are a small fraction of the performance objectives. Cost-effective options for reducing releases further are unlikely to exist. Therefore, releases from the Area 3 RWMS are judged to be as low as reasonably achievable. Comparison of the maximum CA result with the 0.3 mSv CA dose constraint indicates that no action is required to reduce the dose from the Area 3 RWMS and all interacting sources of residual radioactive contamination. The SA maximum mean CA annual TED, 0.02 mSv at 1,000 y, has increased from the approved CA result but remains less than 10% of the dose constraint. The CA TED continues to be due predominantly to inhalation of plutonium-239 resuspended from soils contaminated by nuclear weapons tests conducted near the Area 3 RWMS. The SA results estimated with the Area 3 RWMS version 2.102 model indicate that changes to the PA and CA do not

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 Radioactive Waste Management Site (RWMS) Performance Assessments (PAs) and Composite Analyses (CAs) in fiscal year (FY) 2010. This annual summary report presents data and conclusions from the FY 2010 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) (formerly the Nevada TestSite) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs.

A Corrective Action Investigation (CAI) was performed in several stages from 1999 to 2003, as set forth in the ''Corrective Action Investigation Plan for the Central Nevada Test Area Subsurface Sites, Corrective Action Unit 443'' (DOE/NV, 1999). Groundwater modeling was the primary activity of the CAI. Three phases of modeling were conducted for the Faultless underground nuclear test. The first phase involved the gathering and interpretation of geologic and hydrogeologic data, and inputting the data into a three-dimensional numerical model to depict groundwater flow. The output from the groundwater flow model was used in a transport model to simulate the migration of a radionuclide release (Pohlmann et al., 2000). The second phase of modeling (known as a Data Decision Analysis [DDA]) occurred after NDEP reviewed the first model. This phase was designed to respond to concerns regarding model uncertainty (Pohll and Mihevc, 2000). The third phase of modeling updated the original flow and transport model to incorporate the uncertainty identified in the DDA, and focused the model domain on the region of interest to the transport predictions. This third phase culminated in the calculation of contaminant boundaries for the site (Pohll et al., 2003). Corrective action alternatives were evaluated and an alternative was submitted in the ''Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 443: Central Nevada Test Area-Subsurface'' (NNSA/NSO, 2004). Based on the results of this evaluation, the preferred alternative for CAU 443 is Proof-of-Concept and Monitoring with Institutional Controls. This alternative was judged to meet all requirements for the technical components evaluated and will control inadvertent exposure to contaminated groundwater at CAU 443.

This report is a summary of the history, design and development, procurement, fabrication, installation and operation of the closures used as containment devices on underground nuclear tests at the Nevada TestSite. It also addresses the closure program mothball and start-up procedures. The Closure Program Document Index and equipment inventories, included as appendices, serve as location directories for future document reference and equipment use.

Note: This document was prepared before the NTS was renamed the Nevada National Security Site (August 23, 2010); thus, all references to the site herein remain NTS. Corrective Action Unit (CAU) 98, Frenchman Flat, at the Nevada TestSite (NTS) was the location of ten underground nuclear tests between 1965 and 1971. As a result, radionuclides were released in the subsurface in the vicinity of the test cavities. Corrective Action Unit 98 and other CAUs at the NTS and offsite locations are being investigated. The Frenchman Flat CAU is one of five Underground Test Area (UGTA) CAUs at the NTS that are being evaluated as potential sources of local or regional impact to groundwater resources. For UGTA sites, including Frenchman Flat, contamination in and around the test cavities will not be remediated because it is technologically infeasible due to the depth of the test cavities (150 to 2,000 feet [ft] below ground surface) and the volume of contaminated groundwater at widely dispersed locations on the NTS. Instead, the compliance strategy for these sites is to model contaminant flow and transport, estimate the maximum spatial extent and volume of contaminated groundwater (over a period of 1,000 years), maintain institutional controls, and restrict access to potentially contaminated groundwater at areas where contaminants could migrate beyond the NTS boundaries.

This report documents the result of the US Department of Energy (DOE) Environment, Safety, and Health (ES&H) Progress Assessment of the Nevada TestSite (NTS), Nye County, Nevada. The assessment, which was conducted from July 20 through August 4, 1992, included a selective review of the ES&H management systems and progress of the responsible DOE Headquarters Program Offices; the DOE Nevada Field Office (NV); and the site contractors. The ES&H Progress Assessments are part of the Secretary of Energy`s continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. This report presents a summary of issues and progress in the areas of environment, safety and health, and management.

Accurate representation of geothermal conditions is necessary to determine generation potential of source rocks buried in Railroad Valley. Boreholes, provide the best source of geothermal information, but formation temperature data must be screened for variations caused by drilling. Bottomhole temperatures from wireline logs are affected by initial formation conditions, drilling fluid that moves into the formation while drilling, and lag time between cessation of drilling fluid circulation and acquisition of logs. More accurate indicators of formation conditions are temperatures recorded during drill-stem tests, especially for tests that recovered large amounts of fluid. Over 130 drill-stem tests were examined to establish the viability of this source of data and to determine the geothermal conditions of the Railroad Valley basin. Results indicate that 500 feet or more of fluid recovery on a test is necessary to get a temperature recorded that is not influenced by drilling perturbations. The formation temperature data collected for Railroad Valley indicate the possibility of 2 thermal regimes. A low-temperature gradient regime is probably influenced by meteoric water. The high-temperature gradient regime probably reflects the regional heat flow associated with the thin crust of the Great Basin.

This report is a compilation of the groundwater sampling results from three monitoring wells located near the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada TestSite (NTS), Nye County, Nevada, for calendar year 2007. The NTS is an approximately 3,561 square kilometer (1,375 square mile) restricted-access federal installation located approximately 105 kilometers (65 miles) northwest of Las Vegas, Nevada (Figure 1). Pilot wells UE5PW-1, UE5PW-2, and UE5PW-3 are used to monitor the groundwater at the Area 5 RWMS (Figure 2). In addition to groundwater monitoring results, this report includes information regarding site hydrogeology, well construction, sample collection, and meteorological data measured at the Area 5 RWMS. The disposal of low-level radioactive waste and mixed low-level radioactive waste at the Area 5 RWMS is regulated by U.S. Department of Energy (DOE) Order 435.1, 'Radioactive Waste Management'. The disposal of mixed low-level radioactive waste is also regulated by the state of Nevada under the Resource Conservation and Recovery Act (RCRA) regulation Title 40 Code of Federal Regulations (CFR) Part 265, 'Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities' (CFR, 1999). The format of this report was requested by the Nevada Division of Environmental Protection (NDEP) in a letter dated August 12, 1997. The appearance and arrangement of this document have been modified slightly since that date to provide additional information and to facilitate the readability of the document. The objective of this report is to satisfy any Area 5 RWMS reporting agreements between DOE and NDEP.

Site 300 Site Access Contained Firing Facility (CFF) Continuously Operating Reference Station (CORS) What is Site 300? Lawrence Livermore National Laboratory's Site 300 is an experimental testsite operated by the Lawrence Livermore National Security, LLC, for the Department of Energy's National Nuclear Security Administration. It is situated on 7,000 acres in rural foothills approximately six miles southwest of downtown Tracy and 15 miles southeast of Livermore. Site 300 was established in 1955 as a non-nuclear explosives test facility to support Livermore Laboratory's national security mission. The site gets its name from the early days of Lawrence Livermore, when the main laboratory was called Site 200 and the test facility was Site 300 (Lawrence Berkeley National Laboratory was Site 100). Today, work at Site 300

This report identifies 16 Nevada TestSite (NTS) natural water sources that may be classified by the U.S. Army Corps of Engineers (USACE) as jurisdictional wetlands and identifies eight water sources that may be classified as waters of the United States. These water sources are rare, localized habitats on the NTS that are important to regional wildlife and to isolated populations of water tolerant plants and aquatic organisms. No field investigations on the NTS have been conducted in the past to identify those natural water sources which would be protected as rare habitats and which may fall under regulatory authority of the Clean Water Act (CWA) of 1997. This report identifies and summarizes previous studies of NTS natural water sources, and identifies the current DOE management practices related to the protection of NTS wetlands. This report also presents management goals specific for NTS wetlands that incorporate the intent of existing wetlands legislation, the principles of ecosystem management, and the interests of regional land managers and other stakeholders.

The Underground Test Area (UGTA) Corrective Action Unit (CAU) 97, Yucca Flat/Climax Mine, in the northeast part of the Nevada National Security Site (NNSS) requires environmental corrective action activities to assess contamination resulting from underground nuclear testing. These activities are necessary to comply with the UGTA corrective action strategy (referred to as the UGTA strategy). The corrective action investigation phase of the UGTA strategy requires the development of groundwater flow and contaminant transport models whose purpose is to identify the lateral and vertical extent of contaminant migration over the next 1,000 years. In particular, the goal is to calculate the contaminant boundary, which is defined as a probabilistic model-forecast perimeter and a lower hydrostratigraphic unit (HSU) boundary that delineate the possible extent of radionuclide-contaminated groundwater from underground nuclear testing. Because of structural uncertainty in the contaminant boundary, a range of potential contaminant boundaries was forecast, resulting in an ensemble of contaminant boundaries. The contaminant boundary extent is determined by the volume of groundwater that has at least a 5 percent chance of exceeding the radiological standards of the Safe Drinking Water Act (SDWA) (CFR, 2012).

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada TestSite Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada TestSite will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

The US Geological Survey (USGS) working under an Interagency agreement with the Department of Energy is engaged in a broad geoscience program to assess and identify a potential repository for high level nuclear waste at Yucca Mountain, Nye County, Nevada. The USGS program, referred to as the Yucca Mountain Project, or YMP, consists of integrated geologic, hydrologic and geophysical studies which range in nature from site specific to regional. This report is an evaluation of different acquisition methods for future regional seismic reflection studies to be conducted in the vicinity of Yucca Mountain, located in the southwestern corner of the Nevada TestSite (NTS). In January 1988, field studies were conducted to investigate the feasibility of using the common-depth point (CDP) seismic reflection method to map subsurface geological horizons within the Amargosa Desert, Nye County, Nevada. The goal of the field study was to investigate which seismic reflection method(s) should be used for mapping shallow to lower-crustal horizons. Therefore, a wide-variety of field acquisition parameters were tested, included point versus linear receiver group arrays; Vibroseis (service and trademark of Conoco, Inc.) versus explosive sources; Vibroseis array patterns; and Vibroseis sweep and frequency range. 31 refs., 33 figs., 8 tabs.

Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

Note: This page contains sample records for the topic "test site nye" from the National Library of EnergyBeta (NLEBeta).
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This attachment expands on the general description of the Nevada TestSite (NTS) presented in the Introduction to the Nevada TestSite Environmental Report 2008 (National Security Technologies, LLC [NSTec], 2009a). Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

This appendix to the ''Nevada TestSite Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada TestSite (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada TestSite will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada TestSite Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal.

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

The Nevada TestSite (NTS), located in Nye County, southern Nevada, was the location of 828 announced underground nuclear tests, conducted between 1951 and 1992. Approximately one-third of these tests were detonated near or below the water table. An unavoidable consequence of these testing activities was introducing radionuclides into the subsurface environment, impacting groundwater. Groundwater flows beneath the NTS almost exclusively through interconnected natural fractures in carbonate and volcanic rocks. Information about these fractures is necessary to determine hydrologic parameters for future Corrective Action Unit (CAU)-specific flow and transport models which will be used to support risk assessment calculations for the U.S. Department of Energy, Nevada Operations Office (DOE/NV) Underground Test Area (UGTA) remedial investigation. Fracture data are critical in reducing the uncertainty of the predictive capabilities of CAU-specific models because of their usefulness in generating hydraulic conductivity values and dispersion characteristics used in transport modeling. Specifically, fracture aperture and density (spacing) are needed to calculate the permeability anisotropy of the formations. Fracture mineralogy information is used qualitatively to evaluate diffusion and radionuclide retardation potential in transport modeling. All these data can best be collected through examination of core samples.

Field TestSites Field TestSites Aerial view of the National Wind Technology Center with the Flatiron Mountains in the background NREL's NWTC has numerous test pads available to industry partners for testing wind turbines that range in size from a few hundred kilowatts to several megawatts. PIX 17711. Manufacturers can take advantage of NREL's numerous test pads and the technical expertise of its staff to field test prototypes of small and large wind turbines. Many of the small wind turbines tested at the NWTC are participants in NREL's Small Wind Turbine Independent Test Program. Small and mid-sized turbines field tested at the NWTC include those manufactured by Atlantic Orient Corporation, Bergey Windpower, Southwest Wind Power, Northern Power Systems, Endurance Wind Power Inc., Gaia-Wind Ltd.,

This appendix expands on the general description of the Nevada TestSite (NTS) presented in the Introduction to the Nevada TestSite Environmental Report 2007 (U.S. Department of Energy [DOE], 2008). Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

The Nevada TestSite Environmental Report 2003 was prepared by Bechtel Nevada to meet the requirements and guidelines of the U.S. Department of Energy and the information needs of the public. This report is meant to be useful to members of the public, public officials, regulators, and Nevada TestSite contractors. The Executive Summary strives to present in a concise format the purpose of the document, the NTS mission and major programs, a summary of radiological releases and doses to the public resulting from site operations, a summary of non-radiological releases, and an overview of the Nevada TestSite Environmental Management System. The Executive Summary, combined with the following Compliance Summary, are written to meet all the objectives of the report and to be stand-alone sections for those who choose not to read the entire document.

The feasibility and limitations of surface-to-tunnel seismic telemetry at the Nevada TestSite were explored through field measurements using current technology. Range functions for signaling were determined through analysis of monofrequency seismic signals injected into the earth at various sites as far as 70 km (43 mi) from installations of seismometers in the G-Tunnel complex of Rainier Mesa. Transmitted signal power at 16, 24, and 32 Hz was measured at two locations in G-Tunnel separated by 670 m (2200 ft). Transmissions from 58 surface sites distributed primarily along three azimuths from G-Tunnel were studied. The G-Tunnel noise environment was monitored over the 20-day duration of the field tests. Noise-power probability functions were calculated for 20-s and 280-s seismic-record populations. Signaling rates were calculated for signals transmitted from superior transmitter sites to G-Tunnel. A detection threshold of 13 dB re 1 nm/sup 2/ displacement power at 95% reliability was demanded. Consideration of field results suggests that even for the frequency range used in this study, substantially higher signaling rates are likely to be obtained in future work in view of the present lack of information relevant to hardware-siting criteria and the seismic propagation paths at the Nevada TestSite. 12 references.

The Nevada TestSite Environmental Report (NTSER) 2008 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ NTSERs are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx.

The Nevada TestSite Environmental Report (NTSER) 2008 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ NTSERs are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx.

The Nevada TestSite (NTS) is a large (1,350 square miles) secure site currently operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy and was established in 1951 to provide a venue for testing nuclear weapons. Three areas with a variety of elevation and geological parameters were used for testing, but the largest number of tests was in Yucca Flat. The Yucca Flat area is approximately 5 miles wide and 20 miles long and approximately 460 subsidence craters resulted from testing in this area. The Sedan crater displaced approximately 12 million tons of earth and is the largest of these craters at 1,280 feet across and 320 feet deep. The profiles of Sedan and the other craters offer a wide variety of shapes and depths that are ideally suited for lunar analog testing.

The Nevada TestSite Environmental Report 2007 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada TestSite (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada TestSite Environmental Report Summary 2007. This NTSER was prepared to satisfy DOE Order 231.1A, Environment, Safety and Health Reporting. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This report meets these objectives for the NTS and three offsite Nevada facilities mentioned in this report.

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) directs the management and operation of the Nevada TestSite (NTS). The NTS is the nation's historical testingsite for nuclear weapons from 1951 through 1992 and is currently the nation's unique site for ongoing national-security related missions and high-risk operations. NNSA/NSO strives to provide to the public an understanding of the current activities on the NTS, including environmental monitoring and compliance activities aimed at protecting the public and the environment from radiation hazards and from nonradiological impacts. This document is a summary of the Nevada TestSite Environmental Report (NTSER) for calendar year 2007 (see attached compact disc on inside back cover). The NTSER is a comprehensive report of environmental activities performed at the NTS and offsite facilities over the previous calendar year. It is prepared annually to meet the requirements and guidelines of the U.S. Department of Energy (DOE) and the information needs of NNSA/NSO stakeholders. To provide an abbreviated and more readable version of the NTSER, this summary report is produced. This summary does not include detailed data tables, monitoring methods or design, a description of the NTS environment, or a discussion of all environmental program activities performed throughout the year. The reader may obtain a hard copy of the full NTSER as directed on the inside front cover of this summary report.

This document is a revegetation plan for long-term stabilization (revegetation) of land disturbed by activities associated with the closure of a Bomblet Pit and the Five Points Landfill. Both sites are on the Tonopah Test Range (TTR) located in south-central Nevada. This document contains general reclamation practices and procedures that will be followed during the revegetation of these sites. The revegetation procedures proposed have been developed over several years of research and include the results of reclamation trials at Area 11 and Area 19 on the Nevada TestSite (NTS), and more recently at the Double Tracks (Nellis Air Force Range) reclamation demonstration plots. In addition, the results of reclamation efforts and concurrent research efforts at the Yucca Mountain Project have been considered in the preparation of this revegetation plan.

This document supersedes DOE/NV/25946--801, “Nevada TestSite Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

The Nevada TestSite Environmental Report 2009 was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This and previous years’ Nevada TestSite Environmental Reports (NTSERs) are posted on the NNSA/NSO website at http://www.nv.doe.gov/library/publications/aser.aspx. This NTSER was prepared to satisfy DOE Order DOE O 231.1A, “Environment, Safety and Health Reporting.” Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NNSA/NSO Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This NTSER summarizes data and compliance status for calendar year 2009 at the Nevada TestSite (NTS) and its two support facilities, the North Las Vegas Facility (NLVF) and the Remote Sensing Laboratory (RSL)-Nellis. It also addresses environmental restoration (ER) projects conducted at the Tonopah Test Range (TTR). Through a Memorandum of Agreement, NNSA/NSO is responsible for the oversight of TTR ER projects, and the Sandia Site Office of NNSA (NNSA/SSO) has oversight of all other TTR activities. NNSA/SSO produces the TTR annual environmental report available at http://www.sandia.gov/news/publications/environmental/index.html.

Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

Note: This page contains sample records for the topic "test site nye" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.

The Nevada TestSite Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts.

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada TestSite (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada TestSite (National Security Technologies, LLC, 2007a) requires an annual review to assess the adequacy of the Performance Assessments (PAs) and Composite Analyses (CAs), with the results submitted annually to U.S. Department of Energy (DOE) Office of Environmental Management. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE, 1999a; 2000). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 RWMS PAs and CAs for fiscal year (FY) 2011. This annual summary report presents data and conclusions from the FY 2011 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R and D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) (formerly the Nevada TestSite) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R and D activities were reviewed to determine the adequacy of the CAs. Important developments in FY 2011 include the following: (1) Operation of a new shallow land disposal unit and a new Resource Conservation and Recovery Act (RCRA)-compliant lined disposal unit at the Area 5 RWMS; (2) Development of new closure inventory estimates based on disposals through FY 2011; (3) Evaluation of new or revised waste streams by special analysis; (4) Development of version 2.102 of the Area 3 RWMS GoldSim PA model; and (5) Development of version 4.113 of the Area 5 RWMS GoldSim PA model. Analysis of the latest available data using the Area 5 RWMS v4.113 GoldSim PA model indicates that all performance objectives can be met. The results and conclusions of the Area 5 RWMS PA are judged valid, and there is no need to the revise the PA. The Area 3 RWMS has been in inactive status since July 1, 2006, with the last shipment received in April 2006. In FY 2011, there were no operational changes, monitoring results, or R and D results for the Area 3 RWMS that would impact PA validity. Despite the increase in waste volume and inventory at the Area 3 RWMS since 1996 when the PA was approved, the facility performance evaluated with the Area 3 RWMS PA GoldSim model, version 2.0 (with the final closure inventory), remains well below the performance objectives set forth in U.S. Department of Energy Order DOE O 435.1, 'Radioactive Waste Management' (DOE, 2001). The conclusions of the Area 3 RWMS PA remain valid. A special analysis was prepared to update the PA and CA results for the Area 3 RWMS in FY 2011. Release of the special analysis is planned for FY 2012. The continuing adequacy of the CAs was evaluated with the new models, and no significant changes that would alter CA results or conclusions were found. Inclusion of the Frenchman Flat Underground Test Area (UGTA) results in the Area 5 RWMS CA is scheduled for FY 2016, pending the completion of the closure report for the Frenchman Flat UGTA corrective action unit (CAU) in FY 2015. An industrial site, CAU 547, with corrective action sites near the Area 3 RWMS was found to have a significant plutonium inventory in 2009. CAU 547 will be evaluated for inclusion of future revisions or updates of the Area 3 RWMS CA. The revision of the Area 3 RWMS CA, which will include the UGTA source terms, is expected in FY 2024, following the completion of the Yucca Flat CAU Corrective Action Decision Document, scheduled for FY 2023. Near-term R and D efforts will focus on continuing development of the Are

Geothermal Resource area 9 encompasses all of Nye County, Nevada. Within this area there are many different known geothermal sites ranging in temperature from 70/sup 0/ to over 265/sup 0/ F. Fifteen of the more major sites have been selected for evaluation in this Area Development Plan. Various potential uses of the energy found at each of the resource sites discussed in this Area Development Plan were determined after evaluating the area's physical characteristics, land ownership and land use patterns, existing population and projected growth rates, and transportation facilities, and comparing those with the site specific resource characteristics. The uses considered were divided into five main categories: electrical generation, space heating, recreation, industrial process heat, and agriculture. Within two of these categories certain subdivisions were considered separately. The findings about each of the 15 geothermal sites considered in this Area Development Plan are summarized.

The Nevada Operations Office (NV) is responsible for supporting the nuclear test programs of the Los Alamos and Lawrence Livermore National Laboratories. This support includes the drilling of test holes for nuclear device testing a the Nevada TestSite (NTS). The purpose of this audit was to assess the effectiveness of the Department of Energy's management of test hole inventories at the NTS. Our audit disclosed that NV accumulated a large inventory of unused test holes and approved drilling additional holes for which neither laboratory (Los Alamos nor Livermore) had identified a need. The overdrilling of test holes occurred because NV did not comply with good inventory practices that would have had NV's approving official question the need for, and the timing of, the laboratories' drilling requests. Instead, NV gave perfunctory approval to the laboratories' work orders for drilling test holes, and emphasized keeping two drill rig crews busy and satisfying the laboratories' demands for dedicated drilling personnel. Although NV did not agree that overdrilling had occurred, it has cut back its drilling activities and estimated that this will save abut $7.6 million annually. NV agreed with the recommendations in the report and has taken corrective actions.

The Spent Fuel Test-Climax (SFT-C) is a test of dry geologic storage of spent nuclear reactor fuel. The SFT-C is located at a depth of 420 m in the Climax granitic stock at the Nevada TestSite. Eleven canisters of spent commercial PWR fuel assemblies are to be stored for 3 to 5 years. Additional heat is supplied by electrical heaters, and more than 800 channels of technical information are being recorded. The measurements include rock temperature, rock displacement and stress, joint motion, and monitoring of the ventilation air volume, temperature, and dewpoint.

The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada TestSite (National Security Technologies, LLC 2007a) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs), with the results submitted to the U.S. Department of Energy (DOE) Office of Environmental Management. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE 1999a, 2000). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 RWMS PAs and CAs for fiscal year (FY) 2012. This annual summary report presents data and conclusions from the FY 2012 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs. Important developments in FY 2012 include the following: ? Release of a special analysis for the Area 3 RWMS assessing the continuing validity of the PA and CA ? Development of a new Area 5 RWMS closure inventory estimate based on disposals through FY 2012 ? Evaluation of new or revised waste streams by special analysis ? Development of version 4.114 of the Area 5 RWMS GoldSim PA model The Area 3 RWMS has been in inactive status since July 1, 2006, with the last shipment received in April 2006. The FY 2012 review of operations, facility design, closure plans, monitoring results, and R&D results for the Area 3 RWMS indicates no changes that would impact PA validity. A special analysis using the Area 3 RWMS v2.102 GoldSim PA model was prepared to update the PA results for the Area 3 RWMS in FY 2012. The special analysis concludes that all performance objectives can be met and the Area 3 RWMS PA remains valid. There is no need to the revise the Area 3 RWMS PA. Review of Area 5 RWMS operations, design, closure plans, monitoring results, and R&D activities indicates no significant changes other than an increase in the inventory disposed. The FY 2012 PA results, generated with the Area 5 RWMS v4.114 GoldSim PA model, indicate that there continues to be a reasonable expectation of meeting all performance objectives. The results and conclusions of the Area 5 RWMS PA are judged valid, and there is no need to the revise the PA. A review of changes potentially impacting the CAs indicates that no significant changes occurred in FY 2012. The continuing adequacy of the CAs was evaluated with the new models, and no significant changes that would alter CA results or conclusions were found. The revision of the Area 3 RWMS CA, which will include the Underground Test Area source term (Corrective Action Unit [CAU] 97), is scheduled for FY 2024, following the completion of the Yucca Flat CAU 97 Corrective Action Decision Document/Corrective Action Plan in FY 2016. Inclusion of the Frenchman Flat CAU 98 results in the Area 5 RWMS CA is scheduled for FY 2016, pending the completion of the CAU 98 closure report in FY 2015. Near-term R&D efforts will focus on continuing development of the Area 3 and Area 5 RWMS GoldSim PA/CA and inventory models.

Fifty-two species of freshwater algae were identified in samples collected from the eight known natural springs of the Nevada TestSite. Although several species were widespread, 29 species were site specific. Diatoms provided the greatest variety of species at each spring. Three-fifths of all algal species encountered were diatoms. Well-developed mats of filamentous green algae (Chlorophyta) were common in many of the water tanks associated with the springs and accounted for most of the algal biomass. Major nutrients were adequate, if not abundant, in most spring waters - growth being limited primarily by light and physical habitat. There was some evidence of cesium-137 bioconcentration by algae at several of the springs.

Nevada TestSite - 023 Nevada TestSite - 023 FUSRAP Considered SitesSite: Nevada TestSite (023) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Nevada TestSite was established by the Atomic Energy Commission in the 1950's to conduct field testing of nuclear explosives in connection with the research and development of nuclear weapons. The environmental management activities for this site are under the purview of the Department of EnergyÂżs Nevada Operations Office. The National Nuclear Security Administration is the site landlord and will be responsible for Long Term Stewardship. Also see Documents Related to Nevada TestSite

The Nevada TestSite (NTS) Resource Management Plan (RMP) describes the NTS Stewardship Mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. The NTS Stewardship Mission is to manage the land and facilities at the NTS as a unique and valuable national resource. The RMP has defined goals for twelve resource areas based on the principles of ecosystem management. These goals were established using an interdisciplinary team of DOE/NV resource specialists with input from surrounding land managers, private parties, and representatives of Native American governments. The overall goal of the RMP is to facilitate improved NTS land use management decisions within the Great Basin and Mojave Desert ecoregions.

Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

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3: Nevada TestSite and Off-Site Locations in the State of 3: Nevada TestSite and Off-Site Locations in the State of Nevada EIS-0243: Nevada TestSite and Off-Site Locations in the State of Nevada Summary This EIS evaluates the potential environmental impacts of the management of low-level waste (LLW) at all sites and continue, to the extent practicable, disposal of on- site LLW at the Idaho National Engineering and Environmental Laboratory (INEEL), the Los Alamos National Laboratory (LANL) in New Mexico, the Oak Ridge Reservation (ORR) in Tennessee, and the Savannah River Site (SRS) in South Carolina. Public Comment Opportunities None available at this time. Documents Available for Download November 3, 2003 EIS-0243-SA-02: Supplement Analysis Nevada TestSite and Off-Site Locations in the State of Nevada to Address

The purpose of this Special Analysis (SA) is to determine if the Oak Ridge (OR) Consolidated Edison Uranium Solidification Project (CEUSP) uranium-233 (233U) waste stream (DRTK000000050, Revision 0) is acceptable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The CEUSP 233U waste stream requires a special analysis because the concentrations of thorium-229 (229Th), 230Th, 232U, 233U, and 234U exceeded their NNSS Waste Acceptance Criteria action levels. The acceptability of the waste stream is evaluated by determining if performance assessment (PA) modeling provides a reasonable expectation that SLB disposal is protective of human health and the environment. The CEUSP 233U waste stream is a long-lived waste with unique radiological hazards. The SA evaluates the long-term acceptability of the CEUSP 233U waste stream for near-surface disposal as a two tier process. The first tier, which is the usual SA process, uses the approved probabilistic PA model to determine if there is a reasonable expectation that disposal of the CEUSP 233U waste stream can meet the performance objectives of U.S. Department of Energy Manual DOE M 435.1-1, “Radioactive Waste Management,” for a period of 1,000 years (y) after closure. The second tier addresses the acceptability of the OR CEUSP 233U waste stream for near-surface disposal by evaluating long-term site stability and security, by performing extended (i.e., 10,000 and 60,000 y) modeling analyses, and by evaluating the effect of containers and the depth of burial on performance. Tier I results indicate that there is a reasonable expectation of compliance with all performance objectives if the OR CEUSP 233U waste stream is disposed in the Area 5 RWMS SLB disposal units. The maximum mean and 95th percentile PA results are all less than the performance objective for 1,000 y. Monte Carlo uncertainty analysis indicates that there is a high likelihood of compliance with all performance objectives. Tier II results indicate that the long-term performance of the OR CEUSP 233U waste stream is protective of human health and the environment. The Area 5 RWMS is located in one of the least populated and most arid regions of the U.S. Site characterization data indicate that infiltration of precipitation below the plant root zone at 2.5 meters (8.2 feet) ceased 10,000 to 15,000 y ago. The site is not expected to have a groundwater pathway as long as the current arid climate persists. The national security mission of the NNSS and the location of the Area 5 RWMS within the Frenchman Flat Corrective Action Unit require that access controls and land use restrictions be maintained indefinitely. PA modeling results for 10,000 to 60,000 y also indicate that the OR CEUSP 233U waste stream is acceptable for near-surface disposal. The mean resident air pathway annual total effective dose (TED), the resident all-pathways annual TED, and the acute drilling TED are less than their performance objectives for 10,000 y after closure. The mean radon-222 (222Rn) flux density exceeds the performance objective at 4,200 y, but this is due to waste already disposed at the Area 5 RWMS and is only slightly affected by disposal of the CEUSP 233U. The peak resident all-pathways annual TED from CEUSP key radionuclides occurs at 48,000 y and is less than the 0.25 millisievert performance objective. Disposal of the OR CEUSP 233U waste stream in a typical SLB trench slightly increases PA results. Increasing the depth was found to eliminate any impacts of the OR CEUSP 233U waste stream. Containers could not be shown to have any significant impact on performance due to the long half-life of the waste stream and a lack of data for pitting corrosion rates of stainless steel in soil. The results of the SA indicate that all performance objectives can be met with disposal of the OR CEUSP 233U waste stream in the SLB units at the Area 5 RWMS. The long-term performance of the OR CEUSP 233U waste stream disposed in the near surface is protective of human health

The purpose of this Special Analysis (SA) is to determine if the Oak Ridge (OR) Consolidated Edison Uranium Solidification Project (CEUSP) uranium-233 (233U) waste stream (DRTK000000050, Revision 0) is acceptable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The CEUSP 233U waste stream requires a special analysis because the concentrations of thorium-229 (229Th), 230Th, 232U, 233U, and 234U exceeded their NNSS Waste Acceptance Criteria action levels. The acceptability of the waste stream is evaluated by determining if performance assessment (PA) modeling provides a reasonable expectation that SLB disposal is protective of human health and the environment. The CEUSP 233U waste stream is a long-lived waste with unique radiological hazards. The SA evaluates the long-term acceptability of the CEUSP 233U waste stream for near-surface disposal as a two tier process. The first tier, which is the usual SA process, uses the approved probabilistic PA model to determine if there is a reasonable expectation that disposal of the CEUSP 233U waste stream can meet the performance objectives of U.S. Department of Energy Manual DOE M 435.1-1, “Radioactive Waste Management,” for a period of 1,000 years (y) after closure. The second tier addresses the acceptability of the OR CEUSP 233U waste stream for near-surface disposal by evaluating long-term site stability and security, by performing extended (i.e., 10,000 and 60,000 y) modeling analyses, and by evaluating the effect of containers and the depth of burial on performance. Tier I results indicate that there is a reasonable expectation of compliance with all performance objectives if the OR CEUSP 233U waste stream is disposed in the Area 5 RWMS SLB disposal units. The maximum mean and 95th percentile PA results are all less than the performance objective for 1,000 y. Monte Carlo uncertainty analysis indicates that there is a high likelihood of compliance with all performance objectives. Tier II results indicate that the long-term performance of the OR CEUSP 233U waste stream is protective of human health and the environment. The Area 5 RWMS is located in one of the least populated and most arid regions of the U.S. Site characterization data indicate that infiltration of precipitation below the plant root zone at 2.5 meters (8.2 feet) ceased 10,000 to 15,000 y ago. The site is not expected to have a groundwater pathway as long as the current arid climate persists. The national security mission of the NNSS and the location of the Area 5 RWMS within the Frenchman Flat Corrective Action Unit require that access controls and land use restrictions be maintained indefinitely. PA modeling results for 10,000 to 60,000 y also indicate that the OR CEUSP 233U waste stream is acceptable for near-surface disposal. The mean resident air pathway annual total effective dose (TED), the resident all-pathways annual TED, and the acute drilling TED are less than their performance objectives for 10,000 y after closure. The mean radon-222 (222Rn) flux density exceeds the performance objective at 4,200 y, but this is due to waste already disposed at the Area 5 RWMS and is only slightly affected by disposal of the CEUSP 233U. The peak resident all-pathways annual TED from CEUSP key radionuclides occurs at 48,000 y and is less than the 0.25 millisievert performance objective. Disposal of the OR CEUSP 233U waste stream in a typical SLB trench slightly increases PA results. Increasing the depth was found to eliminate any impacts of the OR CEUSP 233U waste stream. Containers could not be shown to have any significant impact on performance due to the long half-life of the waste stream and a lack of data for pitting corrosion rates of stainless steel in soil. The results of the SA indicate that all performance objectives can be met with disposal of the OR CEUSP 233U waste stream in the SLB units at the Area 5 RWMS. The long-term performance of the OR CEUSP 233U waste stream disposed in the near surface is protective of human health

Six geopressured-geothermal prospects in southern Louisiana were studied in detail to assess their potential use as testsites for the production of geopressure-geothermal energy. Each of the six sites contains substantial quantities of energy. Three of these prospects, Grand Lake, Lake Theriot, and Bayou Hebert, appear to be suitable for a testsite. A summary of the findings is presented.

The Renewable Energy Guy: Q&A with TV's Bill Nye The Renewable Energy Guy: Q&A with TV's Bill Nye The Renewable Energy Guy: Q&A with TV's Bill Nye June 10, 2010 - 11:42am Addthis Bill Nye currently hosts three television shows about science. | Photo courtesy of Bill Nye Bill Nye currently hosts three television shows about science. | Photo courtesy of Bill Nye Lindsay Gsell For years, Bill Nye entertained children on the educational television series "Bill Nye the Science Guy." Using wacky demonstrations, funny music videos and easy to digest lessons, Nye encouraged children to enjoy and appreciate science. The quirky Nye-a scientist, engineer, comedian, author, and inventor-now works to spread the message of renewable energy, and regularly takes on projects to "green" his own Californian home.

The Renewable Energy Guy: Q&A with TV's Bill Nye The Renewable Energy Guy: Q&A with TV's Bill Nye The Renewable Energy Guy: Q&A with TV's Bill Nye June 10, 2010 - 11:42am Addthis Bill Nye currently hosts three television shows about science. | Photo courtesy of Bill Nye Bill Nye currently hosts three television shows about science. | Photo courtesy of Bill Nye Lindsay Gsell For years, Bill Nye entertained children on the educational television series "Bill Nye the Science Guy." Using wacky demonstrations, funny music videos and easy to digest lessons, Nye encouraged children to enjoy and appreciate science. The quirky Nye-a scientist, engineer, comedian, author, and inventor-now works to spread the message of renewable energy, and regularly takes on projects to "green" his own Californian home.

This report inventories the surface distribution of silicic tuffs in Nye, Esmeralda, and Lincoln Counties, NV, based on a review of available literature. The inventory was taken to provide a data base in evaluating tuff sites for the disposal of high-level nuclear waste. Silicic ash-flow tuffs that are about 11 to 34 million years (my) old are widespread in these counties. These rocks are locally deformed by right-lateral movement along Walker Lane and the Las Vegas Shear Zone, and left-lateral movement along a zone from near the Nevada TestSite (NTS) to the Utah border, and are commonly offset by steeply dipping normal faults. The normal faults that bound horsts, grabens, and tilted-fault blocks of the Basin-and-Range Province began to form 30 my ago; some are still active. Tuff distribution is discussed on a regional basis. Tuff thicknesses and alterations, structural complexity, and proximity to recent faulting, recent volcanism, and mineral resources are discussed for each area. Although the literature on which it is based is often incomplete and sketchy, this report is intended to serve as a basis for future, more detailed work that includes initial field inspection, detailed field and laboratory studies, and extrapolations to the subsurface.

Nevada TestSite - June 2007 Nevada TestSite - June 2007 Independent Oversight Inspection, Nevada TestSite - June 2007 June 2007 Inspection of Emergency Management at the Nevada TestSite The U.S. Department of Energy (DOE) Office of Independent Oversight inspected the emergency management program at DOE's Nevada TestSite (NTS) in March-April 2007. The inspection was performed as a joint effort by Independent Oversight's Office of Environment, Safety and Health Evaluations (HS-64) and the Office of Emergency Management Oversight (HS-63). This 2007 inspection found that NSO and NTS organizations have generally continued to improve the site's emergency management program. The most noteworthy program attribute identified during this emergency management inspection is that NSO, NSTec, and JNPO have established and provided the

Nevada TestSite - September 2004 Nevada TestSite - September 2004 Independent Oversight Inspection, Nevada TestSite - September 2004 September 2004 Security and Emergency Management Pilot Integrated Performance Tests at the Nevada TestSite The Secretary of Energy's Office of Independent Oversight and Performance Assurance (OA), within the Office of Security and Safety Performance Assurance, conducted an inspection of safeguards and security and emergency management programs at the U.S. Department of Energy's (DOE) Nevada TestSite (NTS) in July and August 2004. The inspection was performed as a joint effort by the OA Office of Safeguards and Security Evaluations and Office of Emergency Management Oversight. This report discusses the observations related to the emergency management objectives for these two performance

The purpose of the test was to determine the effective coverage of the proposed upgrades to the existing Hanford Site Emergency Alerting System (HSEAS). The upgrades are to enhance the existing HSEAS along the Columbia River from the Vernita Bridge to the White Bluffs Boat Launch as well as install a new alerting system in the 400 Area on the Hanford Site. Five siren sites along the Columbia River and two sites in the 400 Area were tested to determine the site locations that will provide the desired coverage.

The Nevada TestSite (NTS), located in Nye County in southern Nevada, was the location of 928 nuclear tests conducted between 1951 and 1992. Of the total tests, 824 were nuclear tests performed underground. This report describes the approach taken to determine whether any specific, proven, cost-effective technologies currently exist to aid in the removal of the radioactive contaminants from the groundwater, in the stabilization of these contaminants, and in the removal of the source of the contaminants.

Independent Oversight Inspection, Nevada TestSite, Volume 2 - Independent Oversight Inspection, Nevada TestSite, Volume 2 - September 2004 Independent Oversight Inspection, Nevada TestSite, Volume 2 - September 2004 September 2004 Inspection of Emergency Management at the Nevada TestSite The Secretary of Energy's Office of Independent Oversight and Performance Assurance (OA), within the Office of Security and Safety Performance Assurance, conducted an inspection of safeguards and security and emergency management programs at the U.S. Department of Energy's (DOE) Nevada TestSite (NTS) in July and August 2004. The inspection was performed as a joint effort by the OA Office of Safeguards and Security Evaluations and Office of Emergency Management Oversight. This volume discusses the results of the review of the NTS emergency management program.

Oversight Inspection, Nevada TestSite, Summary Report Oversight Inspection, Nevada TestSite, Summary Report - October 2002 Independent Oversight Inspection, Nevada TestSite, Summary Report - October 2002 October 2002 Inspection of Environment, Safety, and Health and Emergency Management at the Nevada TestSite The Secretary of Energy's Office of Independent Oversight and Performance Assurance (OA) conducted an inspection of environment, safety, and health (ES&H) and emergency management programs at the National Nuclear Security Administration (NNSA) Nevada TestSite (NTS) in September and October 2002. The inspection was performed as a joint effort by the OA Office of Environment, Safety and Health Evaluations and the Office of Emergency Management Oversight. Overall, safety management at NTS has substantially improved in the past

Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

Note: This page contains sample records for the topic "test site nye" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.

Nevada TestSite - June 2007 Nevada TestSite - June 2007 Independent Oversight Inspection, Nevada TestSite - June 2007 June 2007 Inspection of Environment, Safety, and Health Programs at the Nevada TestSite The U.S. Department of Energy (DOE) Office of Independent Oversight, within the Office of Health, Safety and Security (HSS), conducted an inspection of environment, safety, and health (ES&H) programs at the DOE Nevada TestSite (NTS) during March and April 2007. The ES&H inspection was performed by Independent Oversight's Office of Environment, Safety and Health Evaluations (HS-64). NSO has some adequate oversight program elements, such as the Facility Representative program, and in several cases NSO is effectively using contract performance measures to drive performance improvements. NSO has

The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Waste Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and NSTec is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 RWMS is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NTS (Figure 2), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan for the Disposal of Low-Level Waste with Regulated Asbestos Waste.'' A requirement of the authorization was that on or before October 9, 1999, a permit was required to be issued. Because of NDEP and NNSA/NSO review cycles, the final permit was issued on April 5, 2000, for the operation of the Area 5 Low-Level Waste Disposal Site, utilizing Pit 7 (P07) as the designated disposal cell. The original permit applied only to Pit 7, with a total design capacity of 5,831 cubic yards (yd{sup 3}) (157,437 cubic feet [ft{sup 3}]). NNSA/NSO is expanding the SWDS to include the adjacent Upper Cell of Pit 6 (P06), with an additional capacity of 28,037 yd{sup 3} (756,999 ft{sup 3}) (Figure 3). The proposed total capacity of ALLW in Pit 7 and P06 will be approximately 33,870 yd{sup 3} (0.9 million ft{sup 3}). The site will be used for the disposal of regulated ALLW, small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. The only waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM). The term asbestiform is used throughout this document to describe this waste. Other TSCA waste (i.e., polychlorinated biphenyls [PCBs]) will not be accepted for disposal at the SWDS. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the U.S. Department of Energy, Nevada Operations Office (DOE/NV) 325

Treatment Plans (STPS) are required for facilities at which the US Department of Energy (DOE) or stores mixed waste, defined by the Federal Facility Compliance Act (FFCAct) as waste containing both a hazardous waste subject to the Resource Conservation and Recovery Act and a radioactive material subject to the Atomic Energy Act. On April 6, 1993, DOE published a Federal Register notice (58 FR 17875) describing its proposed process for developing the STPs in three phases including a Conceptual, a Draft, and a Proposed Site Treatment Plan (PSTP). All of the DOE Nevada Operations Office STP iterations have been developed with the state of Nevada`s input. The options and schedules reflect a ``bottoms-up`` approach and have been evaluated for impacts on other DOE sites, as well as impacts to the overall DOE program. Changes may have occurred in the preferred option and associated schedules between the PSTP, which was submitted to the state of Nevada and US Environmental Protection Agency April 1995, and the Final STP (hereafter referred to as the STP) as treatment evaluations progressed. The STP includes changes that have occurred since the submittal of the PSTP as a result of state-to-state and DOE-to-state discussions.

Nevada TestSite, NV Nevada TestSite, NV EM Project: Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada TestSite Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada TestSite (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5. Disposal operations at Area 3 have been discontinued, but the facility is available for future disposal. The anticipated closure date for Area 3 is 2027. Area 5 is operating and will be expanded to accept future wastes. LLRW and mixed low-level radioactive waste (MLLW) are disposed of in Area 5 in shallow

The DOE Distributed Power Program conducted a pilot test of interconnection test procedures November 12-16, 2001 at Area 25 of the Nevada TestSite (NTS). The objective of this pilot test was to respond to Congressional direction in the Energy and Water Development Appropriations Act of 2001 to complete a distributed power demonstration at the Nevada TestSite and validated interconnection tests in the field. The demonstration consisted of field verification of tests in IEEE P1547 (Draft 7) that are required for interconnection of distributed generation equipment to electrical power systems. Some of the testing has been conducted in a laboratory setting, but the Nevada TestSite provided a location to verify the interconnection tests in the field. The testing also provided valuable information for evaluating the potential for the Nevada TestSite to host future field-testing activities in support of Distributed Energy Resources System Integration R&D.

Nevada TestSite Development Corporation Nevada TestSite Development Corporation WASHINGTON, D.C. - The Department of Energy (DOE) today announced that it will award $300,000 to the Nevada TestSite Development Corporation (NTSDC). This block grant will enable the NTSDC to continue to provide administrative support for rural economic development, renewable energy, aerospace activities, asset management and business incubation. "The Energy Department is a good neighbor to the communities surrounding our sites," Secretary of Energy Spencer Abraham said. "Working with the NTSDC and other community reuse organizations around the country, the Department has retained, expanded or created over 25,000 jobs for workers affected by restructuring efforts at DOE sites."

This Phase II CAIP describes new work needed to potentially reduce uncertainty and achieve increased confidence in modeling results. This work includes data collection and data analysis to refine model assumptions, improve conceptual models of flow and transport in a complex hydrogeologic setting, and reduce parametric and structural uncertainty. The work was prioritized based on the potential to reduce model uncertainty and achieve an acceptable level of confidence in the model predictions for flow and transport, leading to model acceptance by NDEP and completion of the Phase II CAI stage of the UGTA strategy.

This document describes an approach for preliminary (Phase I) flow and transport modeling for the Rainier Mesa/Shoshone Mountain (RMSM) Corrective Action Unit (CAU). This modeling will take place before the planned Phase II round of data collection to better identify the remaining data gaps before the fieldwork begins. Because of the geologic complexity, limited number of borings, and large vertical gradients, there is considerable uncertainty in the conceptual model for flow; thus different conceptual models will be evaluated, in addition to different framework and recharge models. The transport simulations will not be used to formally calculate the Contaminant Boundary at this time. The modeling (Phase II) will occur only after the available data are considered sufficient in scope and quality.

Congressional, State Officials Tour Hanford's TestSite for Safe Congressional, State Officials Tour Hanford's TestSite for Safe Tank Waste Cleanup Congressional, State Officials Tour Hanford's TestSite for Safe Tank Waste Cleanup September 30, 2013 - 12:00pm Addthis Ben Harp, center, manager of HanfordĂ˘Â€Â™s Waste Treatment Plant Start-up and Commissioning Integration, discusses the advantages of ORP's Cold Test Facility to a group of congressional and state legislative staffers during a recent tour. Ben Harp, center, manager of Hanford's Waste Treatment Plant Start-up and Commissioning Integration, discusses the advantages of ORP's Cold Test Facility to a group of congressional and state legislative staffers during a recent tour. RICHLAND, Wash. - EM's Office of River Protection (ORP) recently hosted a group of congressional and state legislative staffers on a tour of the

The Nevada TestSite Environmental Report 2006 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada TestSite (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada TestSite Environmental Report Summary 2006 produced to be a more cost-effective means of distributing information contained in the NTSER to interested DOE stakeholders.

This program focused on installing distributed resources (DR) systems at customer sites, then performing a series of tests based on a selected protocol. Tests included evaluation of heat rate, air and noise emissions, power quality, and an economic analysis for each DR technology in the program.

This map and accompanying cross sections present an updated synthesis of the geologic framework of the Oasis Valley area, a major groundwater discharge site located about 15 km west of the Nevada TestSite. Most of the data presented in this compilation is new geologic map data, as discussed below. In addition, the cross sections incorporate new geophysical data that have become available in the last three years (Grauch and others, 1997; written comm., 1999; Hildenbrand and others, 1999; Mankinen and others, 1999). Geophysical data are used to estimate the thickness of the Tertiary volcanic and sedimentary rocks on the cross sections, and to identify major concealed structures. Large contiguous parts of the map area are covered either by alluvium or by volcanic units deposited after development of the major structures present at the depth of the water table and below. Hence, geophysical data provide critical constraints on our geologic interpretations. A companion paper by Fridrich and others (1999) and the above-cited reports by Hildenbrand and others (1999) and Mankinen and others (1999) provide explanations of the interpretations that are presented graphically on this map. This map covers nine 7.5-minute quadrangles in Nye County, Nevada, centered on the Thirsty Canyon SW quadrangle, and is a compilation of one published quadrangle map (O'Connor and others, 1966) and eight new quadrangle maps, two of which have been previously released (Minor and others, 1997; 1998). The cross sections that accompany this map were drawn to a depth of about 5 km below land surface at the request of hydrologists who are modeling the Death Valley groundwater system.

The U.S. Department of Energy has implemented a program to reclaim lands disturbed by site characterization at Yucca Mountain. Long term goals of the program are to re-establish processes on disturbed sites that will lead to self-sustaining plant communities. The Biological Opinion for Yucca Mountain Site Characterization Studies required that the U.S. Department of Energy develop a Reclamation Standards and Monitoring Plan to evaluate the success of reclamation efforts. According to the Reclamation Standards and Monitoring Plan, reclaimed sites will be monitored periodically, remediated if necessary, and eventually compared to an appropriate reference area to determine whether reclamation goals have been achieved and the site can be released from further monitoring. Plant cover, density, and species richness (success parameters) on reclaimed sites are compared to 60 percent of the values (success criteria) for the same parameters on the reference area. Small sites (less than 0.1 ha) are evaluated for release using qualitative methods while large sites (greater than 0.1 ha) are evaluated using quantitative methods. In the summer of 2000, 31 small sites reclaimed in 1993 and 1994 were evaluated for reclamation success and potential release from further monitoring. Plant density, cover, and species richness were estimated on the C-Well Pipeline, UE-25 Large Rocks testsite, and 29 ground surface facility test pits. Evidence of erosion, reproduction and natural recruitment, exotic species abundance, and animal use (key attributes) also were recorded for each site and used in success evaluations. The C-Well Pipeline and ground surface facility test pits were located in a ''Larrea tridentata - Ephedra nevadensis'' vegetation association while the UE-25 Large Rocks testsite was located in an area dominated by ''Coleogyne ramosissima and Ephedra nevadensis''. Reference areas in the same vegetation associations with similar slope and aspect were chosen for comparison to the reclaimed sites. Sixty percent of the reference area means for density, cover, and species richness were compared to the estimated means for the reclaimed sites. Plant density, cover, and species richness at the C-Well Pipeline and UE-25 Large Rocks testsite were greater than the success criteria and all key attributes indicated the sites were in acceptable condition. Therefore, these two sites were recommended for release from further monitoring. Of the 29 ground surface facility test pits, 26 met the criterion for density, 21 for cover, and 23 for species richness. When key attributes and conditions of the plant community near each pit were taken into account, 27 of these pits were recommended for release. Success parameters and key attributes at ground surface facility test pits 19 and 20 were inadequate for site release. Transplants of native species were added to these two sites in 2001 to improve density, cover, and species richness.

Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada TestSite (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program.

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A generic test of retrievable geologic storage of spent fuel assemblies in an underground chamber is being conducted at the Nevada TestSite. The horizontal shrinkage of the pillars is not explainable, but the vertical pillar stresses are easily understood. A two-phase project was initiated to estimate the in-situ deformability of the Climax granite and to refine the in-situ stress field data, and to model the mine-by. (DLC)

This quality assurance project plan (QAPjP) describes the measures that shall be taken to ensure that the environmental data collected during characterization and closure activities of Resource Conservation and Recovery Act (RCRA) Industrial Sites at the Nevada TestSite (NTS) are meaningful, valid, defensible, and can be used to achieve project objectives. These activities are conducted by the US Department of Energy Nevada Operations Office (DOE/NV) under the Nevada Environmental Restoration (ER) Project. The Nevada ER Project consists of environmental restoration activities on the NTS, Tonopah Test Range, Nellis Air Force Range, and eight sites in five other states. The RCRA Industrial Sites subproject constitutes a component of the Nevada ER Project. Currently, this QAPjP is limited to the seven RCRA Industrial Sites identified within this document that are to be closed under an interim status and pertains to all field-investigation, analytical-laboratory, and data-review activities in support of these closures. The information presented here supplements the RCRA Industrial Sites Project Management Plan and is to be used in conjunction with the site-specific subproject sampling and analysis plans.

This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 540: Spill Sites, Nevada TestSite, Nevada. This CR complies with the requirements of the 'Federal Facility Agreement and Consent Order' (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Corrective Action Unit 540 is located within Areas 12 and 19 of the Nevada TestSite and is comprised of the following Corrective Action Sites (CASs): CAS 12-44-01, ER 12-1 Well Site Release; CAS 12-99-01, Oil Stained Dirt; CAS 19-25-02, Oil Spill; CAS 19-25-04, Oil Spill; CAS 19-25-05, Oil Spill; CAS 19-25-06, Oil Spill; CAS 19-25-07, Oil Spill; CAS 19-25-08, Oil Spills (3); and CAS 19-44-03, U-19bf Drill Site Release. The purpose of this CR is to provide documentation supporting recommendations of no further action for the CASs within CAU 540. To achieve this, the following actions were performed: (1) Reviewed the current site conditions, including the concentration and extent of contamination; (2) Performed closure activities to address the presence of substances regulated by 'Nevada Administrative Code' 445A.2272 (NAC, 2002); and (3) Documented Notice of Completion and closure of CAU 540 issued by the Nevada Division of Environmental Protection.

Area 5 LLRW & MLLW Disposal Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada TestSite Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada TestSite (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5. Disposal operations at Area 3 have been discontinued, but the facility is available for future disposal. The anticipated closure date for Area 3 is 2027. Area 5 is operating and will be expanded to accept future wastes. LLRW and mixed low-level radioactive

Multi-sitetesting is a popular and effective way to increase test throughput and reduce test costs. We present a test throughput model, in which we focus on wafer testing, and consider parameters like test time, index time, abort-on-fail, and contact yield. Conventional multi-sitetesting requires sufficient ATE resources, such as ATE channels, to allow to test multiple SOCs in parallel. In this paper, we design and optimize on-chip DfT, in order to maximize the test throughput for a given SOC and ATE. The on-chip DfT consists of an E-RPCT wrapper, and, for modular SOCs, module wrappers and TAMs. We present experimental results for a Philips SOC and several ITC'02 SOC Test Benchmarks.

The US Department of Energy (DOE) proposes to modify an existing reactor containment building (decommissioned Plutonium Recycle Test Reactor (PRTR) 309 Building) to provide ground test capability for the prototype SP-100 reactor. The 309 Building (Figure 1.1) is located in the 300 Area on the Hanford Site in Washington State. The National Environmental Policy Act (NEPA) requires that Federal agencies assess the potential impacts that their actions may have on the environment. This Environmental Assessment describes the consideration given to environmental impacts during reactor concept and testsite selection, examines the environmental effects of the DOE proposal to ground test the nuclear subsystem, describes alternatives to the proposed action, and examines radiological risks of potential SP-100 use in space. 73 refs., 19 figs., 7 tabs.

The development history of the data acquisition and data analysis software is discussed in this report. The software development occurred between 1978 and 1984 in support of solar energy module testing at the Jet Propulsion Laboratory's Parabolic Dish TestSite, located within Edwards Test Station. The development went through incremental stages, starting with a simple single-user BASIC set of programs, and progressing to the relative complex multi-user FORTRAN system that was used until the termination of the project. Additional software in support of testing is discussed including software in support of the meteorological subsystem and the Test Bed Concentrator Control Console interface. Conclusions and recommendations for further development are discussed.

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada TestSite (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE

Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection,' establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada TestSite (NTS), related (on-site or off-site) U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration off-site projects. This NTS RPP promulgates the radiation protection standards, limits, and program requirements for occupational exposure to ionizing radiation resulting from NNSA/NSO activities at the NTS and other operational areas as stated in 10 CFR 835.1(a). NNSA/NSO activities (including design, construction, operation, and decommissioning) within the scope of this RPP may result in occupational exposures to radiation or radioactive material. Therefore, a system of control is implemented through specific references to the site-specific NV/YMP RCM. This system of control is intended to ensure that the following criteria are met: (1) occupational exposures are maintained as low as reasonably achievable (ALARA), (2) DOE's limiting values are not exceeded, (3) employees are aware of and are prepared to cope with emergency conditions, and (4) employees are not inadvertently exposed to radiation or radioactive material.

A Tortoise Population Monitoring Study was initiated to determine and monitor the density of desert tortoises (Gopherus agassizii) on the Nevada TestSite. Quadrat sampling was conducted following methodology described in the Draft Desert Tortoise Recovery Plan (FWS, 1993). So few tortoises were found that densities could not be calculated. Based on estimates of capture probabilities and densities from other studies, it was determined that 1-km{sup 2} (0.4 mi{sup 2}) plots did not contain enough tortoises for estimating densities with the Recovery Plan methods. It was recommended that additional surveys on the Nevada TestSite using those methods not be conducted. Any future efforts to monitor desert tortoise densities should start by identifying other possible methods, determining their relative power to detect changes, and estimating their cost.

This document presents a measurement uncertainty analysis for the instruments used in the ECS-2 test series conducted for the Savannah River Site at the Idaho National Engineering Laboratory. The tests are a series of downflow dryout heat transfer experiments designed to support computer code development and verification in setting limits for the Savannah River Production reactors. The measurements include input current, voltage, and power; air and water flows, fluid and metal temperatures, and absolute and differential pressures. An analysis of the data acquisition system as it relates to these measurements is also included. 18 refs., 6 figs., 12 tabs.

In the past, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada TestSite has been performed by the Radiological Health Instrumentation Department. Calibration and performance tests on the PM-700 personnel portal monitor were performed but there was no test program for the VM-250 vehicle portal monitor because it had never been put into service. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no program in place to test them quarterly. In April of 2007, the Material Control and Accountability (MC&A) Manager at the time decided that the program needed to be strengthened and MC&A took over performance testing of all SNM portal monitoring equipment. This paper will discuss the following activities associated with creating a performance testing program: changing the culture, learning the systems, writing procedures, troubleshooting/repairing, validating the process, control of equipment, acquisition of new systems, and running the program.

A team from the Remote Sensing Laboratory conducted an aerial radiological survey of the US Department of Energy's Nevada TestSite including three neighboring areas during August and September 1994. The survey team measured the terrestrial gamma radiation at the Nevada TestSite to determine the levels of natural and man-made radiation. This survey included the areas covered by previous surveys conducted from 1962 through 1993. The results of the aerial survey showed a terrestrial background exposure rate that varied from less than 6 microroentgens per hour (mR/h) to 50 mR/h plus a cosmic-ray contribution that varied from 4.5 mR/h at an elevation of 900 meters (3,000 feet) to 8.5 mR/h at 2,400 meters (8,000 feet). In addition to the principal gamma-emitting, naturally occurring isotopes (potassium-40, thallium-208, bismuth-214, and actinium-228), the man-made radioactive isotopes found in this survey were cobalt-60, cesium-137, europium-152, protactinium-234m an indicator of depleted uranium, and americium-241, which are due to human actions in the survey area. Individual, site-wide plots of gross terrestrial exposure rate, man-made exposure rate, and americium-241 activity (approximating the distribution of all transuranic material) are presented. In addition, expanded plots of individual areas exhibiting these man-made contaminations are given. A comparison is made between the data from this survey and previous aerial radiological surveys of the Nevada TestSite. Some previous ground-based measurements are discussed and related to the aerial data. In regions away from man-made activity, the exposure rates inferred from the gamma-ray measurements collected during this survey agreed very well with the exposure rates inferred from previous aerial surveys.

On-site inspection (OSI) is one of the four verification provisions of the Comprehensive Nuclear Test Ban Treaty (CTBT). Under the provisions of the CTBT, once the Treaty has entered into force, any signatory party can request an on-site inspection, which can then be carried out after approval (by majority voting) of the Executive Council. Once an OSI is approved, a team of 40 inspectors will be assembled to carry out an inspection to ''clarify whether a nuclear weapon test explosion or any other nuclear explosion has been carried out in violation of Article I''. One challenging aspect of carrying out an on-site inspection (OSI) in the case of a purported underground nuclear explosion is to detect and locate the underground effects of an explosion, which may include an explosion cavity, a zone of damaged rock, and/or a rubble zone associated with an underground collapsed cavity. The CTBT (Protocol, Section II part D, paragraph 69) prescribes several types of geophysical investigations that can be carried out for this purpose. One of the methods allowed by the CTBT for geophysical investigation is referred to in the Treaty Protocol as ''resonance seismometry''. This method, which was proposed and strongly promoted by Russia during the Treaty negotiations, is not described in the Treaty. Some clarification about the nature of the resonance method can be gained from OSI workshop presentations by Russian experts in the late 1990s. Our understanding is that resonance seismometry is a passive method that relies on seismic reverberations set up in an underground cavity by the passage of waves from regional and teleseismic sources. Only a few examples of the use of this method for detection of underground cavities have been presented, and those were done in cases where the existence and precise location of an underground cavity was known. As is the case with many of the geophysical methods allowed during an OSI under the Treaty, how resonance seismology really works and its effectiveness for OSI purposes has yet to be determined. For this experiment, we took a broad approach to the definition of ''resonance seismometry''; stretching it to include any means that employs passive seismic methods to infer the character of underground materials. In recent years there have been a number of advances in the use of correlation and noise analysis methods in seismology to obtain information about the subsurface. Our objective in this experiment was to use noise analysis and correlation analysis to evaluate these techniques for detecting and characterizing the underground damage zone from a nuclear explosion. The site that was chosen for the experiment was the Mackerel test in Area 4 of the former Nevada TestSite (now named the Nevada National Security Site, or NNSS). Mackerel was an underground nuclear test of less than 20 kT conducted in February of 1964 (DOENV-209-REV 15). The reason we chose this site is because there was a known apical cavity occurring at about 50 m depth above a rubble zone, and that the site had been investigated by the US Geological Survey with active seismic methods in 1965 (Watkins et al., 1967). Note that the time delay between detonation of the explosion (1964) and the time of the present survey (2010) is nearly 46 years - this would not be typical of an expected OSI under the CTBT.

The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada TestSite (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells.

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Nevada TestSite (NTS), conducted June 22 through July 10, 1987. The Survey is being conducted by a multidisciplinary team of environmental specialists led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team members are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the NTS. The Survey covers all environment media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations and activities performed at the NTS, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain environmental problems identified during its on-site activities. The Sampling and Analysis Plan is being executed by the Battelle Columbus Division under contract with DOE. When completed, the results will be incorporated into the NTS Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the NTS Survey. 165 refs., 42 figs., 52 tabs.

Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada TestSite: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was implemented. (6) At CAS 09-23-01, Area 9 Gravel Gertie, a UR was implemented. (7) At CAS 09-34-01, Underground Detection Station, no work was performed.

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Analysis of data from 60 wells in and around the Nevada TestSite, including 16 in the Yucca Mountain area, indicates a thermal regime characterized by large vertical and lateral gradients in heat flow. Estimates of heat flow indicate considerable variation on both regional and local scales. The variations are attributable primarily to hydrologic processes involving interbasin flow with a vertical component of (seepage) velocity (volume flux) of a few mm/yr. Apart from indicating a general downward movement of water at a few mm/yr, the reults from Yucca Mountain are as yet inconclusive. The purpose of the study was to determine the suitability of the area for proposed repository sites.

RADIOLOGICAL/NUCLEAR COUNTERMEASURES TEST AND EVALUATION COMPLEX, NEVADA TESTSITE The U.S. Department of Homeland Security (DHS) is the Federal organization charged with defending the borders of the United States under the authority the Homeland Security Act of 2002 (Public Law 107-296). The DHS requested the National Nuclear Security Administration (NNSA) to develop at the Nevada TestSite (NTS) a complex for testing and evaluating countermeasures for interdicting potential terrorist attacks using radiological and/or nuclear weapons of mass destruction. In response to that request, NNSA proposes to construct, operate, and maintain the Radiological/Nuclear Countermeasures Test and Evaluation Complex (Rad/NucCTEC). NNSA has prepared an Environmental Assessment (DOE/EA-1499) (EA) which analyzes the potential

Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2004. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2005) and DOE Order 231.1A, Environment, Safety, and Health Reporting (DOE 2004b).

Corrective Action Unit (CAU) 537 is identified in the ''Federal Facility Agreement and Consent Order'' (FFACO) of 1996 as Waste Sites. CAU 537 is located in Areas 3 and 19 of the Nevada TestSite, approximately 65 miles northwest of Las Vegas, Nevada, and consists of the following two Corrective Action Sites (CASs): CAS 03-23-06, Bucket; Yellow Tagged Bags; and CAS 19-19-01, Trash Pit. CAU 537 closure activities were conducted in April 2007 according to the FFACO and Revision 3 of the Sectored Clean-up Work Plan for Housekeeping Category Waste Sites (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2003). At CAS 03-23-06, closure activities included removal and disposal of a 15-foot (ft) by 15-ft by 8-ft tall wooden shed containing wood and metal debris and a 5-gallon plastic bucket containing deteriorated plastic bags with yellow radioactive contamination tape. The debris was transported to the Area 9 U10c Landfill for disposal after being screened for radiological contamination according to the ''NV/YMP Radiological Control Manual'' (NNSA/NSO, 2004). At CAS 19-19-01, closure activities included segregation, removal, and disposal of non-friable, non-regulated asbestos-containing material (ACM) and construction debris. The ACM was determined to be non-friable by waste characterization samples collected prior to closure activities. The ACM was removed and double-bagged by licensed, trained asbestos workers and transported to the Area 9 U10c Landfill for disposal. Construction debris was transported in end-dump trucks to the Area 9 U10c Landfill for disposal. Closure activities generated sanitary waste/construction debris and ACM. Waste generated during closure activities was appropriately managed and disposed. Waste characterization sample results are included as Appendix A of this report, and waste disposition documentation is included as Appendix B of this report. Copies of the Sectored Housekeeping Site Closure Verification Forms for CAS 03-23-06 and CAS 19-19-01 are included as Appendix C of this report. These forms include before and after photographs of the sites, descriptions and removal status of waste, and waste disposal information. CAU 537, Waste Sites, was closed by characterizing and disposing of debris. The purpose of this CR is to summarize the completed closure activities, document appropriate waste disposal, and confirm that the closure standards were met.

An evaluation of groundwater monitoring at non-Nevada TestSite underground nuclear testsites raised questions about the potential for radionuclide migration from the Faultless event and how to best monitor for such migration. With its long standing interest in the Faultless area and background in Nevada hydrogeology, the Desert Research Institute conducted a field investigation in FY92 to address the following issues: The status of chimney infilling (which determines the potential for migration); the best level(s) from which to collect samples from the nearby monitoring wells, HTH-1 and HTH-2; the status of hydraulic heads in the monitoring well area following records of sustained elevated post-shot heads. The field investigation was conducted from July 27 to 31 and August 4 to 7, 1992. Temperature and electrical conductivity logging were performed in HTH-1, HTH-2, and UC-1-P-2SR. Water samples were collected from HTH-1 and HTH-2. Lawrence Livermore National Laboratory (LLNL) also collected samples during the July trip, including samples from UC-1-P-2SR. This report presents the data gathered during these field excursions and some preliminary conclusions. Full interpretation of the data in light of the issues listed above is planned for FY93.

Near-surface heater tests were run in the Eleana Formation at the Nevada TestSite, in an effort to evaluate argillaceous rock for nuclear waste storage. The main test, which employed a full-scale heater with a thermal output approximating commercial borosilicate waste, was designed to operate for several months. Two smaller, scaled tests were run prior to the full-scale test. This report develops the thermal scaling laws, describes the pretest thermal and thermomechanical analysis conducted for these two tests, and discusses the material properties data used in the analyses. In the first test, scaled to a large heater of 3.5 kW power, computed heater temperatures were within 7% of measured values for the entire 96-hour test run. The second test, scaled to a large heater having 5.0 kW power, experienced periodic water in-flow onto the heater, which tended to damp the temperature. For the second test, the computed temperatures were within 7% of measured for the first 20 hours. After this time, the water effect became significant and the measured temperatures were 15 to 20% below those predicted. On the second test, rock surface spallation was noted in the bore hole above the heater, as predicted. The scaled tests indicated that in-situ argillite would not undergo major thermostructural failure during the follow-on, 3.5 kW, full-scale test. 24 figures, 6 tables.

Detailed specifications which must be complied with in the construction of the ERDA Test Facilities at the East Mesa Site for geothermal resource investigations in Imperial Valley, California are presented for use by prospective bidders for the construction contract. The principle construction work includes a 700 gpm cooling tower with its associated supports and equipment, pipelines from wells, electrical equipment, and all earthwork. (LCL)

The LGF Spill Test Facility at Frenchman Flat, Nevada TestSite, is being constructed by the United States Department of Energy (DOE). In this Environmental Assessment, environmental consequences of spilling hazardous materials in the Frenchman Flat basin are evaluated and mitigations and recommendations are stated in order to protect natural resources and reduce land-use impacts. Guidelines and restrictions concerning spill-test procedures will be determined by the LGF Test Facility Operations Manager and DOE based on toxicity documentation for the test material, provided by the user, and mitigations imposed by the Environmental Assessment. In addition to Spill Test Facility operational procedures, certain assumptions have been made in preparation of this document: no materials will be considered for testing that have cumulative, long-term persistence in the environment; spill tests will consist of releases of 15 min or less; and sufficient time will be allowed between tests for recovery of natural resources. Geographic limits to downwind concentrations of spill materials were primarily determined from meteorological data, human occupational exposure standards to hazardous materials and previous spill tests. These limits were established using maximum spill scenarios and environmental impacts are discussed as worst case scenarios; however, spill-test series will begin with smaller spills, gradually increasing in size after the impacts of the initial tests have been evaluated.

A test of retrievable dry geologic storage of spent fuel assemblies from an operating commercial nuclear reactor is underway at the Nevada TestSite. This generic test is located 420 m below the surface in the Climax granitic stock. Eleven canisters of spent fuel approximately 2.3 years out of reactor core (about 2 kW/canister thermal output) will be emplaced in a storage drift along with 6 electrical simulator canisters and their effects will be compared. Two adjacent drifts will contain electrical heaters, which will be operated to simulate within the test array the thermal field of a large repository. The test objectives, technical concepts and rationale, and details of the test are stated and discussed.

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada TestSite (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the US Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring Programs conducted by the US Environmental Protection Agency's (EPA) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this tenth combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations.

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada TestSite (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the U.S. Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring programs conducted by the U.S. Environmental Protection Agency's (EPA's) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this eleventh combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations.

Prior to 1989, annual reports of environmental monitoring and assessment results for the Nevada TestSite (NTS) were prepared in two separate parts. Onsite effluent monitoring and environmental monitoring results were reported in an onsite report prepared by the U.S. Department of Energy, Nevada Operations Office (DOE/NV). Results of the Offsite Radiological Surveillance and Long-Term Hydrological Monitoring programs conducted by the U.S. Environmental Protection Agency's (EPA's) Laboratory (various names) in Las Vegas, Nevada, were reported separately by that Agency. Beginning with the 1989 Annual Site Environmental Report for the NTS, these two documents were combined into a single report to provide a more comprehensive annual documentation of the environmental protection activities conducted for the nuclear testing program and other nuclear and non-nuclear operations at the NTS. The two agencies have coordinated preparation of this eleventh combined onsite and offsite report through sharing of information on environmental surveillance and releases as well as meteorological, hydrological, and other supporting data used in dose-estimation calculations.

Corrective Action Unit (CAU) 536 is located in Area 3 of the Nevada TestSite. CAU 536 is listed in the Federal Facility Agreement and Consent Order of 1996 as Area 3 Release Site, and comprises a single Corrective Action Site (CAS): {sm_bullet} CAS 03-44-02, Steam Jenny Discharge The Nevada Division of Environmental Protection (NDEP)-approved corrective action alternative for CAS 03-44-02 is clean closure. Closure activities included removing and disposing of total petroleum hydrocarbon (TPH)- and polyaromatic hydrocarbon (PAH)-impacted soil, soil impacted with plutonium (Pu)-239, and concrete pad debris. CAU 536 was closed in accordance with the NDEP-approved CAU 536 Corrective Action Plan (CAP), with minor deviations as approved by NDEP. The closure activities specified in the CAP were based on the recommendations presented in the CAU 536 Corrective Action Decision Document (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2004). This Closure Report documents CAU 536 closure activities. During closure activities, approximately 1,000 cubic yards (yd3) of hydrocarbon waste in the form of TPH- and PAH-impacted soil and debris, approximately 8 yd3 of Pu-239-impacted soil, and approximately 100 yd3 of concrete debris were generated, managed, and disposed of appropriately. Additionally, a previously uncharacterized, buried drum was excavated, removed, and disposed of as hydrocarbon waste as a best management practice. Waste minimization techniques, such as the utilization of laboratory analysis to characterize and classify waste streams, were employed during the performance of closure

Department of Energy (DOE) Orders require each DOE site to develop onsite transportation safety documents (OTSDs). The Nevada TestSite approach divided all onsite transfers into two groups with each group covered by a standalone OTSD identified as Non-Nuclear and Nuclear. The Non-Nuclear transfers involve all radioactive hazardous material in less than Hazard Category (HC)-3 quantities and all chemically hazardous materials. The Nuclear transfers involve all radioactive material equal to or greater than HC-3 quantities and radioactive material mated with high explosives regardless of quantity. Both OTSDs comply with DOE O 460.1B requirements. The Nuclear OTSD also complies with DOE O 461.1A requirements and includes a DOE-STD-3009 approach to hazard analysis (HA) and accident analysis as needed. All Nuclear OTSD proposed transfers were determined to be non-equivalent and a methodology was developed to determine if “equivalent safety” to a fully compliant Department of Transportation (DOT) transfer was achieved. For each HA scenario, three hypothetical transfers were evaluated: a DOT-compliant, uncontrolled, and controlled transfer. Equivalent safety is demonstrated when the risk level for each controlled transfer is equal to or less than the corresponding DOT-compliant transfer risk level. In this comparison the typical DOE-STD-3009 risk matrix was modified to reflect transportation requirements. Design basis conditions (DBCs) were developed for each non-equivalent transfer. Initial DBCs were based solely upon the amount of material present. Route-, transfer-, and site-specific conditions were evaluated and the initial DBCs revised as needed. Final DBCs were evaluated for each transfer’s packaging and its contents.

Sandia National Laboratories (SNL) operates the Tonopah Test Range for the Department of Energy's (DOE) Weapons Ordnance Program. Thes annual report (calendar year 1997) summarizes the compliance status to environmental regulations applicable at the site including those statutes that govern air and water quality, waste management, cleanup of contaminated areas, control of toxic substances, and adherence to requirements as related to the National Environmental Policy Act. In compliance with DOE orders, SNL also conducts environmental surveillance for radiological and nonradiological contaminants. SNL's responsibility for environmental surveillance extends only to those activities performed by SNL or under its direction. Annual radiological and nonradiological routine releases and unplanned releases (occurrences) are also summarized. This report has been prepared as required by DOE Order 5400.1, General Environmental Protection Program.

Sandia National Laboratories (SNL) operates the Tonopah Test Range (TTR) for the Department of Energy (DOE) Weapons Ordnance Program. This annual report (calendar year 1998) summarizes the compliance status to environmental regulations applicable at the site including those statutes that govern air and water quality, waste management cleanup of contaminated areas, control of toxic substances, and adherence to requirements as related to the National Environmental Policy Act (NEPA). In compliance with DOE orders, SNL also conducts environmental surveillance for radiological and nonradiological contaminants. SNL's responsibility for environmental surveillance at TTR extends only to those areas where SNL activities are carried out. Annual radiological and nonradiological routine releases and unplanned releases (occurrences) are also summarized. This report has been prepared in accordance with DOE Order 5400.1, General Environmental Protection Program (DOE 1990a).

Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

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The Nevada TestSite (NTS) located in south central Nevada encompasses approximately 3,561 square kilometers and straddles two major North American deserts, Mojave and Great Basin. Transitional areas between the two desert types have been created by gradients in elevation, precipitation, temperature, and soils. From 1996-1998, more than 1,500 ecological landform units were sampled at the NTS for numerous biotic and abiotic parameters. These data provide a basis for spatial evaluations of biodiversity over landscape scales at the NTS. Species diversity maps (species richness vs. species abundance) have been produced. Differences in ecosystem diversity at the ecoregion, alliance, association, and ecological landform unit levels are presented. Spatial distribution maps of species presence and abundance provide evidence of where transition zones occur and the resulting impact on biodiversity. The influences of abiotic factors (elevation, soil, precipitation) and anthropogenic disturbance on biodiversity are assessed.

FIELD FIELD INVESTIGATION AT THE FAULTLESS SITE CENTRAL NEVADA TEST AREA DOEINV/10845--T3 DE93 005915 by JennyB. Chapman, Thdd M. Mihevc and Brad Lyles Water Resources Center Desert Research Institute DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsi- bility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Refer- ence herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom- mendation, or favoring

This Corrective Action Decision Document (CADD) has been prepared for Corrective Action Unit (CAU) 204 Storage Bunkers, Nevada TestSite (NTS), Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE); and the U.S. Department of Defense (FFACO, 1996). The NTS is approximately 65 miles (mi) north of Las Vegas, Nevada (Figure 1-1). The Corrective Action Sites (CASs) within CAU 204 are located in Areas 1, 2, 3, and 5 of the NTS, in Nye County, Nevada (Figure 1-2). Corrective Action Unit 204 is comprised of the six CASs identified in Table 1-1. As shown in Table 1-1, the FFACO describes four of these CASs as bunkers one as chemical exchange storage and one as a blockhouse. Subsequent investigations have identified four of these structures as instrumentation bunkers (CASs 01-34-01, 02-34-01, 03-34-01, 05-33-01), one as an explosives storage bunker (CAS 05-99-02), and one as both (CAS 05-18-02). The six bunkers included in CAU 204 were primarily used to monitor atmospheric testing or store munitions. The ''Corrective Action Investigation Plan (CAIP) for Corrective Action Unit 204: Storage Bunkers, Nevada TestSite, Nevada'' (NNSA/NV, 2002a) provides information relating to the history, planning, and scope of the investigation; therefore, it will not be repeated in this CADD. This CADD identifies potential corrective action alternatives and provides a rationale for the selection of a recommended corrective action alternative for each CAS within CAU 204. The evaluation of corrective action alternatives is based on process knowledge and the results of investigative activities conducted in accordance with the CAIP (NNSA/NV, 2002a) that was approved prior to the start of the Corrective Action Investigation (CAI). Record of Technical Change (ROTC) No. 1 to the CAIP (approval pending) documents changes to the preliminary action levels (PALs) agreed to by the Nevada Division of Environmental Protection (NDEP) and DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This ROTC specifically discusses the radiological PALs and their application to the findings of the CAU 204 corrective action investigation.

The Nevada TestSite (NTS) covers approximately 3300 km{sup 2} of high desert and is located approximately 100 km northwest of Las Vegas, Nevada. Soil contaminated by plutonium exists on the NTS and surrounding areas from safety tests conducted in the 1950s and 1960s. About 150 curies of contamination have been measured over 1200 hectares of land surface. Most contamination is found in the top 5 cm of soil but may be found deep as 25 cm. The cost of conventional removal and disposal of the full soil volume has been estimated at over $500,000,000. This study is directed toward minimizing the volume of waste which must be further processed and disposed of by precisely controlling soil removal depth. The following soil removal machines were demonstrated at the NTS: (1) a CMI Corporation Model PR-500FL pavement profiler, (2) a CMI Corporation Model Tr-225B trimmer reclaimer, (3) a Caterpillar Model 623 elevating scraper equipped with laser depth control, (4) a Caterpillar Model 14G motor grader equipped with laser depth control, (5) a Caterpillar Model 637 auger scraper, and (6) a XCR Series Guzzler vacuum truck. 5 refs., 5 figs.

This paper describes the activities required to modify a facility and the process of characterizing, repackaging, and preparing for shipment the Nevada TestSite’s (NTS) legacy transuranic (TRU) waste in 58 oversize boxes (OSB). The waste, generated at other U.S. Department of Energy (DOE) sites and shipped to the NTS between 1974 and 1990, requires size-reduction for off-site shipment and disposal. The waste processing approach was tailored to reduce the volume of TRU waste by employing decontamination and non-destructive assay. As a result, the low-level waste (LLW) generated by this process was packaged, with minimal size reduction, in large sea-land containers for disposal at the NTS Area 5 Radioactive Waste Management Complex (RWMC). The remaining TRU waste was repackaged and sent to the Idaho National Laboratory Consolidation Site for additional characterization in preparation for disposal at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. The DOE National Nuclear Security Administration Nevada Site Office and the NTS Management and Operating (M&O) contractor, NSTec, successfully partnered to modify and upgrade an existing facility, the Visual Examination and Repackaging Building (VERB). The VERB modifications, including a new ventilation system and modified containment structure, required an approved Preliminary Documented Safety Analysis prior to project procurement and construction. Upgrade of the VERB from a radiological facility to a Hazard Category 3 Nuclear Facility required new rigor in the design and construction areas and was executed on an aggressive schedule. The facility Documented Safety Analysis required that OSBs be vented prior to introduction into the VERB. Box venting was safely completed after developing and implementing two types of custom venting systems for the heavy gauge box construction. A remotely operated punching process was used on boxes with wall thickness of up to 3.05 mm (0.120 in) to insert aluminum bronze filters and sample ports to prevent sparking during penetration. A remotely operated cold-drilling process with self-drilling, self-tapping titanium coated spark-resistant filters was used for boxes with wall thickness of up to 6.35 mm (0.25 in). The box headspace was sampled for the presence of flammable gases. To further accelerate the project schedule, an innovative treatment process was used. Several of the OSBs were re-assayed and determined to be mixed low-level waste (MLLW) which allowed treatment, followed by disposal in the Mixed Waste Disposal Unit at the NTS Area 5 Radioactive Waste Management Complex (RWMC). The MLLW boxes were certified using real-time radiography and overpacked into custom-built polyethylene-lined macroencapsulation containers. The polyethylene-lined lid was welded to the poly-lined box using automatically controlled resistance heating through embedded wiring in the lid. The work was performed under the existing Documented Safety Analysis since plastic welding is accomplished at low temperature and does not introduce the risks of other macroencapsulation processes, such as welding stainless steel containers. The macroencapsulation process for MLLW not only accelerated the schedule by reducing the number of boxes requiring size reduction, but it also resulted in significantly improved safety with as low as reasonable achievable levels of exposure to workers plus reduced cost by eliminating the need to perform repackaging in the VERB.

Two water-cooled isobutane condensers, one with 2 tubes and one with 40 tubes, were subjected to field tests at the East Mesa Geothermal TestSite to assess relative heat transfer performance in both surface evaporator and direct-contact evaporator modes. The five groups of tests established that field performance was below earlier laboratory-determined levels and that direct-contact evaporator mode performance was poorer than that for the surface evaporator mode. In all test situations, fluted condenser tubes performed better than smooth condenser tubes. Cooling water quality had no significant effect on performance, but brine preflash in the direct-contact mode did promote some relative performance improvement. Important implications of these results for binary geothermal power plants are that (1) working-fluid-side impurities can significantly degrade heat transfer performance of the power plant condensers and (2) provisions for minimizing such impurities may be required.

The amount of each size particle in a given soil is called the particle-size distribution (PSD), and the way it feels to the touch is called the soil texture. Sand, silt, and clay are the three particle sizes of mineral material found in soils. Sand is the largest sized particle and it feels gritty; silt is medium sized and it feels floury; and clay is the smallest and if feels sticky. Knowing the particle-size distribution of a soil sample helps to understand many soil properties such as how much water, heat, and nutrients the soil will hold, how fast water and heat will move through the soil, and what kind of structure, bulk density and consistence the soil will have. Furthermore, the native particle-size distribution of the soil in the vicinity of ground zero of a nuclear detonation plays a major role in nuclear fallout. For soils that have a high-sand content, the near-range fallout will be relatively high and the far-range fallout will be relatively light. Whereas, for soils that have a high-silt and high-clay content, the near-range fallout will be significantly lower and the far-range fallout will be significantly higher. As part of a program funded by the Defense Threat Reduction Agency (DTRA), the Lawrence Livermore National Laboratory (LLNL) has recently measured the PSDs from the various major areas at the Nevada TestSite where atmospheric detonations and/or nuclear weapon safety tests were performed back in the 50s and 60s. The purpose of this report is to document those results.

This report presents the results of one of a series of Technical Safety Appraisals (TSAs) being conducted of Department of Energy (DOE) operations (nuclear and non-nuclear) by the Assistant Secretary of Environment, Safety and Health (ES&H), Office of Safety Appraisals. These TSAs are one of the initiatives announced by the Secretary of Energy on September 18, 1985, to enhance the DOE`s environment, safety, and health program. This TSA report focuses on the safety and health operations of the Nevada Operations Office (NV) at the Nevada TestSite (NTS), which was conducted concurrently, with and supporting a Tiger Team Assessment. The total effort of all the Tiger Team assessment, including environmental and manager evaluations, is reported in the Tiger Team Report, issued January 1990. The assessment of the NTS began November 5, 1989 with the briefing of the Tiger Team in Las Vegas at the Nevada Operations Office. The TSA team evaluation was conducted November 6--17, and November 26--December 1, 1989 at the NTS.

The Nevada TestSite-Directed Research, Development, and Demonstration (SDRD) program completed a very successful year of research and development activities in FY 2005. Fifty new projects were selected for funding this year, and five FY 2004 projects were brought to conclusion. The total funds expended by the SDRD program were $5.4 million, for an average per project cost of just under $100,000. Two external audits of SDRD accounting practices were conducted in FY 2005. Both audits found the program's accounting practices consistent with the requirements of DOE Order 413.2A, and one included the observation that the NTS contractor ''did an exceptional job in planning and executing year-start activities.'' Highlights for the year included: the filing of 18 invention disclosures for intellectual property generated by FY 2005 projects; programmatic adoption of 17 FY 2004 SDRD-developed technologies; participation in the tri-lab Laboratory Directed Research and Development (LDRD) and SDRD program review that was broadly attended by NTS, NNSA, LDRD, and U.S. Department of Homeland Security representatives; peer reviews of all FY 2005 projects; and the successful completion of 55 R&D projects, as presented in this report.

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada TestSite. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2008 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities.

This Corrective Action Decision Document/Closure Report has been prepared for Corrective Action Unit (CAU) 370, T-4 Atmospheric TestSite, located in Area 4 at the Nevada TestSite, Nevada, in accordance with the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 370 is comprised of Corrective Action Site (CAS) 04-23-01, Atmospheric TestSite T-4. The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 370 due to the implementation of the corrective action of closure in place with administrative controls. To achieve this, corrective action investigation (CAI) activities were performed from June 25, 2008, through April 2, 2009, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 370: T-4 Atmospheric TestSite and Record of Technical Change No. 1.

Borehole Imaging of In Situ Stress Tests at Mirror Lake Research Site Borehole Imaging of In Situ Stress Tests at Mirror Lake Research Site Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Borehole Imaging of In Situ Stress Tests at Mirror Lake Research Site Author U.S. Geological Survey Published U.S. Geological Survey, 2013 DOI Not Provided Check for DOI availability: http://crossref.org Online Internet link for Borehole Imaging of In Situ Stress Tests at Mirror Lake Research Site Citation U.S. Geological Survey. Borehole Imaging of In Situ Stress Tests at Mirror Lake Research Site [Internet]. 2013. U.S. Geological Survey. [cited 2013/10/16]. Available from: http://water.usgs.gov/ogw/bgas/toxics/ml_bips.html Retrieved from "http://en.openei.org/w/index.php?title=Borehole_Imaging_of_In_Situ_Stress_Tests_at_Mirror_Lake_Research_Site&oldid=688729"

This Closure Report summarizes the corrective actions which were completed at the Corrective Action Sites within Corrective Action Unit 349 Area 12 at the Nevada TestSite. Current site descriptions, observations and identification of wastes removed are included on FFACO Corrective Action Site housekeeping closure verification forms.

Monitoring and surveillance on and around the Nevada TestSite (NTS) by US Department of Energy (DOE) contractors and NTS user organizations during 1995 indicated that operations on the NTS were conducted in compliance with applicable federal and DOE regulations and guidelines. All discharges of radioactive liquids remained onsite in containment ponds, and there was no indication of potential migration of radioactivity to the offsite area through groundwater. Surveillance around the NTS indicated that airborne radioactivity from diffusion, evaporation of effluents, or resuspension was not detectable offsite, and no measurable net exposure to members of the offsite population was detected through the offsite dosimetry program. There were no nonradiological releases to the offsite area. Hazardous wastes were shipped offsite to approved disposal facilities. Compliance with the various regulations stemming from the National Environmental Policy Act (NEPA) is being achieved and, where mandated, permits for air and water effluents and waste management have been obtained from the appropriate agencies. Cooperation with other agencies has resulted in seven different consent orders and agreements. Support facilities at off-NTS locations complied with the requirements of air quality permits and state or local wastewater discharge and hazardous waste permits.

Monitoring and surveillance, on and around the Nevada TestSite, (NTS) by US Department of Energy (DOE) contractors and NTS user organizations during 1997, indicated that operations on the NTS were conducted in compliance with applicable DOE, state, and federal regulations and guidelines. All discharges of radioactive liquids remained onsite in containment ponds, and there was no indication of potential migration of radioactivity to the offsite area through groundwater. Surveillance around the NTS indicated that airborne radioactivity from diffusion, evaporation of liquid effluents, or resuspension of soil was not detectable offsite, and exposure above existing background to members of the offsite population was not measured by the offsite monitoring program. Using the US Environmental Protection Agency`s (EPA`s) Clean Air Package 1988 (CAP88)-PC model and NTS radionuclide emissions and environmental monitoring data, the calculated effective dose equivalent (EDE) to the maximally exposed individual offsite would have been 0.089 mrem. Hazardous wastes were shipped offsite to approved disposal facilities.

Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

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Nevada National Security Site Nuclear Testing Artifacts Become Part Nevada National Security Site Nuclear Testing Artifacts Become Part of U.S. Cultural Archive Nevada National Security Site Nuclear Testing Artifacts Become Part of U.S. Cultural Archive April 1, 2012 - 12:00pm Addthis Stanchions are among the remnants of Smoky Tower. Stanchions are among the remnants of Smoky Tower. LAS VEGAS, NV - The Nevada National Security Site's (NNSS) historic Smoky site may soon join a long list of former nuclear testing locations eligible for inclusion in the National Register of Historic Places. The Desert Research Institute (DRI) is currently working alongside the Nevada Site Office (NSO) to determine the eligibility of Smoky and a number of other EM sites slated for cleanup and closure. "In the last year, we've conducted assessments at over 30 EM sites,"

The Area 3 Radioactive Waste Management Site (RMWS) at the Nevada TestSite (NTS) is managed and operated by National Security Technologies, LLC (NSTec) for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the interim closure plan for the Area 3 RWMS, which was presented in the Integrated Closure and Monitoring Plan (ICMP) (DOE, 2005). The format and content of this plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). The major updates to the plan include a new closure date, updated closure inventory, the new institutional control policy, and the Title II engineering cover design. The plan identifies the assumptions and regulatory requirements, describes the disposal sites and the physical environment in which they are located, presents the design of the closure cover, and defines the approach and schedule for both closing and monitoring the site. The Area 3 RWMS accepts low-level waste (LLW) from across the DOE Complex in compliance with the NTS Waste Acceptance Criteria (NNSA/NSO, 2006). The Area 3 RWMS accepts both packaged and unpackaged unclassified bulk LLW for disposal in subsidence craters that resulted from deep underground tests of nuclear devices in the early 1960s. The Area 3 RWMS covers 48 hectares (119 acres) and comprises seven subsidence craters--U-3ax, U-3bl, U-3ah, U-3at, U-3bh, U-3az, and U-3bg. The area between craters U-3ax and U-3bl was excavated to form one large disposal unit (U-3ax/bl); the area between craters U-3ah and U-3at was also excavated to form another large disposal unit (U-3ah/at). Waste unit U-3ax/bl is closed; waste units U-3ah/at and U-3bh are active; and the remaining craters, although currently undeveloped, are available for disposal of waste if required. This plan specifically addresses the closure of the U-3ah/at and the U-3bh LLW units. A final closure cover has been placed on unit U-3ax/bl (Corrective Action Unit 110) at the Area 3 RWMS. Monolayer-evapotranspirative closure cover designs for the U-3ah/at and U-3bh units are provided in this plan. The current-design closure cover thickness is 3 meters (10 feet). The final design cover will have an optimized cover thickness, which is expected to be less than 3 m (10 ft). Although waste operations at the Area 3 RWMS have ceased at the end of June 2006, disposal capacity is available for future disposals at the U-3ah/at and U-3bh units. The Area 3 RWMS is expected to start closure activities in fiscal year 2025, which include the development of final performance assessment and composite analysis documents, closure plan, closure cover design for construction, cover construction, and initiation of the post-closure care and monitoring activities. Current monitoring at the Area 3 RWMS includes monitoring the cover of the closed mixed waste unit U-3ax/bl as required by the Nevada Department of Environmental Protection, and others required under federal regulations and DOE orders. Monitoring data, collected via sensors and analysis of samples, are needed to evaluate radiation doses to the general public, for performance assessment maintenance, to demonstrate regulatory compliance, and to evaluate the actual performance of the RWMSs. Monitoring provides data to ensure the integrity and performance of waste disposal units. The monitoring program is designed to forewarn management and regulators of any failure and need for mitigating actions. The plan describes the program for monitoring direct radiation, air, vadose zone, biota, groundwater, meteorology, and subsidence. The requirements of post-closure cover maintenance and monitoring will be determined in the final closure plan.

A Test of the Construction Pier Aug. 8, 2005 @ UHH and ML Site Y.Asaoka w/ Sunny and Jamie as the pallet. HPM guy load the block by himself, but this is impossible for us to do same thing. Carrying Test the shackle, the hole of the strip on the block was a little bit enlarged. #12;Placing Test @ ML Site (1

Monitoring and surveillance on and around the Nevada TestSite (NTS) by US Department of Energy (DOE) contractors and NTS user organizations during 1996 indicated that operations on the NTS were conducted in compliance with applicable DOE, state, and federal regulations and guidelines. All discharges of radioactive liquids remained onsite in containment ponds, and there was no indication of potential migration of radioactivity to the offsite area through groundwater. Surveillance around the NTS indicated that airborne radioactivity from diffusion, evaporation of liquid effluents, or resuspension of soil was not detectable offsite, and exposure above background to members of the offsite population was not measured by the offsite monitoring program. Using the US Environmental Protection Agency`s (EPA) Clean Air Package 1988 (CAP88)PC model and NTS radionuclide emissions and environmental monitoring data, the calculated effective dose equivalent (EDE) to the maximally exposed individual offsite would have been 0.11 mrem. This value is less than 2 percent of the federal dose limit prescribed for radionuclide air emissions. Any person receiving this dose would also have received 144 mrem from natural background radiation. There were no nonradiological releases to the offsite area. Hazardous wastes were shipped offsite to approved disposal facilities. Compliance with the various regulations stemming from the National Environmental Policy Act (NEPA) is being achieved and, where mandated, permits for air and water effluents and waste management have been obtained from the appropriate agencies. Cooperation with other agencies has resulted in seven different consent orders and agreements. Support facilities at off-NTS locations have complied with the requirements of air quality permits and state or local wastewater discharge and hazardous waste permits as mandated for each location.

''Ensemble requirements'' in surface chemistry refer to the number and shape of contiguous empty sites necessary for chemisorption of a particular molecule. Ensemble effects can play a major role in directing the course of surface reactions, leading, for example, to dramatic changes in catalytic selectivity when the active metal component is diluted upon alloying with an inert metal. We will review here fundamental surface science studies that have attempted to probe this site size requirement by diluting active sites on a single crystal surface with an inert metal overlayer. We will emphasize recent results in our lab on the interaction of simple molecules (CO, H/sub 2/, O/sub 2/) with Cu-, Ag-, and Bi-dosed Pt(111). Theoretical models based upon Monte-Carlo simulations will be summarized which, when compared to such data, allow more accurate determination of ensemble sizes. These models predict uptake curves that deviate strongly from the commonly used (1-theta)/sup A/ law (A = number of sites in ensemble), which is valid only for an array of isolated ensembles. 32 refs., 3 figs.

This Streamlined Approach for Environmental Restoration Plan identifies the activities required for the closure of Corrective Action Unit 116, Area 25 Test Cell C Facility. The Test Cell C Facility is located in Area 25 of the Nevada TestSite approximately 25 miles northwest of Mercury, Nevada.

This Streamlined Approach for Environmental Restoration plan addresses the action necessary for the clean closure of Corrective Action Unit 461 (Test Area Joint Test Assembly Sites) and Corrective Action Unit 495 (Unconfirmed Joint Test Assembly Sites). The Corrective Action Units are located at the Tonopah Test Range in south central Nevada. Closure for these sites will be completed by excavating and evaluating the condition of each artillery round (if found); detonating the rounds (if necessary); excavating the impacted soil and debris; collecting verification samples; backfilling the excavations; disposing of the impacted soil and debris at an approved low-level waste repository at the Nevada TestSite

This Corrective Action Investigation Plan (CAIP) contains project-specific information for conducting site investigation activities at Corrective Action Unit (CAU) 554: Area 23 Release Site, Nevada TestSite, Nevada. Information presented in this CAIP includes facility descriptions, environmental sample collection objectives, and criteria for the selection and evaluation of environmental samples. Corrective Action Unit 554 is located in Area 23 of the Nevada TestSite, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 554 is comprised of one Corrective Action Site (CAS), which is: 23-02-08, USTs 23-115-1, 2, 3/Spill 530-90-002. This site consists of soil contamination resulting from a fuel release from underground storage tanks (USTs). Corrective Action Site 23-02-08 is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation prior to evaluating corrective action alternatives and selecting the appropriate corrective action for this CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document for CAU 554. Corrective Action Site 23-02-08 will be investigated based on the data quality objectives (DQOs) developed on July 15, 2004, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; and contractor personnel. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 554.

The Validation Test House at the Solar Energy Research Institute in Golden, Colorado, is being used to collect performance data for analysis/design tool validation as part of the DOE Passive Solar Class A Performance Evaluation Program.

The problems associated with reinjecting spent geothermal brines are currently under investigation. This effort has included field tests of injection water to evaluate treating equipment effectiveness at the Niland Geothermal Test Loop. Membrane filter tests were conducted on fluids from the settling tanks, from the test loop, from the clarifier and at the injection well head (Magmamax No. 3). From this and other information concerning the injection interval, pressure, temperature and well history, an attempt to predict a well half life was made. The results of these calculations were not in agreement with observed well performance. An attempt with some apparent success has been made to understand the possible source of these discrepancies. The cyclic nature of the injection history dictated by need for descaling the test loop, followed by apparent partial recovery of injection acceptance, has led to a theory that is under investigation concerning effect of reheating the injection fluid containing amorphous particulate silica by the reservoir rock and fluid during well shut-in. Preliminary tests indicate some of this finely divided silica may be redisolving with consequent reduction in reservoir damage, and that two widely spaced injection wells in an alternating mode may provide low-cost, long-life injection capacity at Niland and similar geothermal projects.

A radionuclide tracer test was conducted in 1963 by the U.S. Geological Survey at the Project Gnome underground nuclear testsite, approximately 40 km southeast of Carlsbad, New Mexico. The tracer study was carried out under the auspices of the U.S. Atomic Energy Commission (AEC) to study the transport behavior of radionuclides in fractured rock aquifers. The Culebra Dolomite was chosen for the test because it was considered to be a reasonable analogue of the fractured carbonate aquifer at the Nevada TestSite (NTS), the principal location of U.S. underground nuclear tests. Project Gnome was one of a small number of underground nuclear tests conducted by the AEC at sites distant from the NTS. The Gnome device was detonated on December 10, 1961 in an evaporate unit at a depth of 360 m below ground surface. Recently, the U.S. Department of Energy (DOE) implemented an environmental restoration program to characterize, remediate, and close these offsite nuclear test areas. An early step in this process is performance of a preliminary risk analysis of the hazard posed by each site. The Desert Research Institute has performed preliminary hydrologic risk evaluations for the groundwater transport pathway at Gnome. That evaluation included the radioactive tracer test as a possible source because the test introduced radionuclides directly into the Culebra Dolomite, which is the only aquifer at the site. This report presents a preliminary evaluation of the radionuclide tracer test as a source for radionuclide migration in the Culebra Dolomite. The results of this study will assist in planning site characterization activities and refining estimates of the radionuclide source for comprehensive models of groundwater transport st the Gnome site.

Planning Bill Nye The Science Guy's Climate Research Lab at Chabot Space Planning Bill Nye The Science Guy's Climate Research Lab at Chabot Space and Science Center Speaker(s): Andrew Anway David Bloom Date: September 24, 2008 - 12:00pm Location: 90-3075 Seminar Host/Point of Contact: Allan Chen Sometime in 2009, the Chabot Space and Science Center hopes to debut a new museum exhibition tentatively titled Bill Nye The Science Guy's Climate Research Lab, subtitle, Mission Possible: Reduce the CO2. The interactive show is anchored by science educator Bill Nye the Science Guy, is aimed towards children and families. It will explain the basic science behind climate change, and its potential effects on humans and the rest of the biosphere, while exploring some ways of reducing greenhouse gas emissions, both what we can do now, and advanced technologies that may someday play a

Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

Note: This page contains sample records for the topic "test site nye" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
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The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office manages two low-level Radioactive Waste Management Sites at the Nevada TestSite. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. This report summarizes characterization and monitoring work pertinent to the 92-Acre Area in the southeast part of the Area 5 Radioactive Waste Management Sites. The decades of characterization and assessment work at the Area 5 RWMS indicate that the access controls, waste operation practices, site design, final cover design, site setting, and arid natural environment contribute to a containment system that meets regulatory requirements and performance objectives for the short- and long-term protection of the environment and public. The available characterization and Performance Assessment information is adequate to support design of the final cover and development of closure plans. No further characterization is warranted to demonstrate regulatory compliance. U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is proceeding with the development of closure plans for the six closure units of the 92-Acre Area.

Bechtel Nevada; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

IlONITORING REPORT FOR THE NEVADA TESTSITE IlONITORING REPORT FOR THE NEVADA TESTSITE AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS January through December 1975 Nonitoring Operations Division Environmental Monitoring and Support Laboratory U.S. ENVIRONMENTAL PROTECTION AGENCY Las Vegas, Nevada 89114 APRIL 1976 This work performed under a Memorandum of Understanding No. AT(26-1)-539 for the U . S . ENERGY RESEARCH & DEVELOPMENT ADMINISTRATION EMSL-LV-5 39-4 May 1976 ENVIRONMENTAL 14ONITORING REPORT FOR THE NEVADA TESTSITE AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS January through December I975 Monitoring Operations Division Environmental Monitoring and Support Laboratory U.S. ENVIRONMENTAL PROTECTION AGENCY Las Vegas, Nevada 89114 APRIL 1976 This work performed under a Memorandum of

The purpose of this report is to provide documentation of the completed corrective action and to provide data confirming the corrective action. The corrective action was performed in accordance with the approved Corrective Action Plan (CAP) (U.S. Department of Energy [DOE], 1999) and consisted of clean closure by excavation and disposal. The Area 15 Quonset Hut 15-11 was formerly used for storage of farm supplies including pesticides, herbicides, and fertilizers. The Area 23 Quonset Hut 800 was formerly used to clean pesticide and herbicide equipment. Steam-cleaning rinsate and sink drainage occasionally overflowed a sump into adjoining drainage ditches. One ditch flows south and is referred to as the quonset hut ditch. The other ditch flows southeast and is referred to as the inner drainage ditch. The Area 23 Skid Huts were formerly used for storing and mixing pesticide and herbicide solutions. Excess solutions were released directly to the ground near the skid huts. The skid huts were moved to a nearby location prior to the site characterization performed in 1998 and reported in the Corrective Action Decision Document (CADD) (DOE, 1998). The vicinity and site plans of the Area 23 sites are shown in Figures 2 and 3, respectively.

Corrective Action Unit (CAU) 139 is located in Areas 3, 4, 6, and 9 of the Nevada TestSite, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 139 is comprised of the seven corrective action sites (CASs) listed below: (1) 03-35-01, Burn Pit; (2) 04-08-02, Waste Disposal Site; (3) 04-99-01, Contaminated Surface Debris; (4) 06-19-02, Waste Disposal Site/Burn Pit; (5) 06-19-03, Waste Disposal Trenches; (6) 09-23-01, Area 9 Gravel Gertie; and (7) 09-34-01, Underground Detection Station. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives with the exception of CASs 09-23-01 and 09-34-01. Regarding these two CASs, CAS 09-23-01 is a gravel gertie where a zero-yield test was conducted with all contamination confined to below ground within the area of the structure, and CAS 09-34-01 is an underground detection station where no contaminants are present. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for the other five CASs where information is insufficient. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 4, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 139.

The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada TestSite locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Rulison site in west-central Colorado was the location of an underground detonation of a 40-kiloton nuclear device in 1969. The test took place 2,568 m below ground surface in the Mesaverde Formation. Though located below the regional water table, none of the bedrock formations at the site yielded water during hydraulic tests, indicating extremely low permeability conditions. The scenario evaluated was the migration of radionuclides from the blast-created cavity through the Mesaverde Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. The transport calculations are most sensitive to changes in the mean groundwater velocity and the correlation scale of hydraulic conductivity, with transport of strontium and cesium also sensitive to the sorption coefficient.

This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 538, Spill Sites, located at the Nevada TestSite (NTS) in Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. The corrective action sites (CASs) within CAU 538 are located within Areas 2, 3, 6, 12, and 23 of the NTS. The purpose of this CR is to provide documentation for the absence of contamination or that the closure objectives have been met for each CAS within CAU 538.

Local Event - Nevada TestSite, Las Vegas, NV Local Event - Nevada TestSite, Las Vegas, NV Local Event - Nevada TestSite, Las Vegas, NV October 25, 2013 9:00AM PDT National Day of Remembrance Local Event Where: National Atomic Testing Museum 755 E Flamingo Rd Las Vegas, NV 89119 On June 11th, 2013, Senators Mark Udall (D-CO) and Lamar Alexander (R-TN) introduced a bipartisan resolution to designate October 30 as the fifth annual National Day of Remembrance for former nuclear weapons workers and uranium miners who proudly served their country starting with the Manhattan Project through present day. Representatives from the DOE, Federal Government, and Atomic Testing Museum will speak on behalf of former workers. Admission to the National Atomic Testing Museum will be free for the day. Local coordinators will have a booth and conduct outreach on the

The Spent Fuel Test-Climax (SFT-C) is located at a depth of 420 m in the Climax granite at the Nevada TestSite. The test array contains 11 canistered PWR fuel assemblies, plus associated electrical simulators and electrical heaters. There are nearly 900 channels of thermal, radiation, stress, displacement, and test control instrumentation. This paper is a general status report on the test, which started in May 1980.

As prescribed in the Pahute Mesa Corrective Action Investigation Plan (CAIP) (DOE/NV, 1999) and Appendix VI of the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended February 2008), the ultimate goal of transport analysis is to develop stochastic predictions of a contaminant boundary at a specified level of uncertainty. However, because of the significant uncertainty of the model results, the primary goal of this report was modified through mutual agreement between the DOE and the State of Nevada to assess the primary model components that contribute to this uncertainty and to postpone defining the contaminant boundary until additional model refinement is completed. Therefore, the role of this analysis has been to understand the behavior of radionuclide migration in the Pahute Mesa (PM) Corrective Action Unit (CAU) model and to define, both qualitatively and quantitatively, the sensitivity of such behavior to (flow) model conceptualization and (flow and transport) parameterization.

This report documents transport data and data analyses for Yucca Flat/Climax Mine CAU 97. The purpose of the data compilation and related analyses is to provide the primary reference to support parameterization of the Yucca Flat/Climax Mine CAU transport model. Specific task objectives were as follows: • Identify and compile currently available transport parameter data and supporting information that may be relevant to the Yucca Flat/Climax Mine CAU. • Assess the level of quality of the data and associated documentation. • Analyze the data to derive expected values and estimates of the associated uncertainty and variability. The scope of this document includes the compilation and assessment of data and information relevant to transport parameters for the Yucca Flat/Climax Mine CAU subsurface within the context of unclassified source-term contamination. Data types of interest include mineralogy, aqueous chemistry, matrix and effective porosity, dispersivity, matrix diffusion, matrix and fracture sorption, and colloid-facilitated transport parameters.

This document presents a summary and framework of available transport data and other information directly relevant to the development of the Rainier Mesa/Shoshone Mountain (RMSM) Corrective Action Unit (CAU) 99 groundwater transport model. Where appropriate, data and information documented elsewhere are briefly summarized with reference to the complete documentation.

This document presents a summary and framework of the available hydrologic data and other information directly relevant to the development of the Rainier Mesa/Shoshone Mountain (RMSM) Corrective Action Unit (CAU) 99 groundwater flow models. Where appropriate, data and information documented elsewhere are briefly summarized with reference to the complete documentation.

Radiocarbon determinations have been used in the past to estimate the ages of groundwater from the Paleozoic aquifer underlying the Nevada TestSite and adjacent areas. We measured the concentrations of {sup 230}Th, {sup 232}Th, {sup 234}U and {sup 238}U in several water samples taken from the wells and spring at the Nevada TestSite and calculated the {sup 230}Th ages. 2 refs.

This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO (1996), CASs are sites potentially requiring corrective action(s), and may include solid waste management units, individual disposal sites, or release sites. Corrective Action Units consist of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP will be used in conjunction with the Work Plan for Leachfield Corrective Action Units: Nevada TestSite and Tonopah Test Range, Nevada (DOE/NV, 1998c), hereafter referred to as the Leachfield Work Plan. Under the FFACO, a work plan is an optional planning document that provides information for a CAU or group of CAUs where significant commonality exists. This CAIP contains CAU-specific information including a facility description, environmental sample collection objectives, and the criteria for conducting site investigation activities at CAU 500. This CAIP addresses one of three leachfield systems associated with Test Cell A, which is located in Area 25 at the Nevada TestSite (NTS). The NTS is approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada (see Leachfield Work Plan Figure 1-1). Corrective Action Unit 500 is comprised of the Test Cell A Septic System (CAS 25-04-05) and the associated leachfield system presented in Figure 1-1 (FFACO, 1996).

Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2003. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2003) and DOE Order 231.1 Chg 2., Environment, Safety, and Health Reporting (DOE 1996).

Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, oversees TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2002. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 5400.1, General Environmental Protection Program (DOE 1990) and DOE Order 231.1, Environment, Safety, and Health Reporting (DOE 1996).

Distribution and characteristics of Pu-bearing radioactive particles throughout five soil profiles from Nuclear Site (NS) 201 were investigated. Concentrations of /sup 239/ /sup 240/Pu and /sup 241/Am decreased with depth and most of the contamination was contained in the top 5 cm except in profile 4 where it extended to 10 cm. The mean activity ratio of /sup 239/ /sup 240/Pu to /sup 241/Am and its standard error were 5.8 +- 0.3 (N=42). Most of the total radioactivity of the soils was contributed by 0.25 to 2 mm sand size fraction which comprised 20 to 50% by weight of the soils. The radioactive particles in the 0.25 to 2 mm size fraction occurred as spherical glass particles or as glass coatings on sand particles. The glass coatings had gas voids in the matrix but were not as porous as the radioactive particles from NS 219. After impact grinding the >0.25-mm size fractions for one hour, 85% of the initial activity in a NS 201 sample remained with the particles on the 0.25 mm sieve, whereas in the NS 219 sample only 10% remained. The results show that the radioactive particles from NS 201 were much more stable against the impact grinding force than those from NS 219. Therefore, the NS 201 soils would be expected to have a lower probability of producing respirable-size radioactive particles by saltation during wind erosion. 19 references, 3 figures, 3 tables.

Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

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United continued this past year to assist the utilities and the Gas Research Institute in the review and selection of sites for data monitoring. Each of these sites will be instrumented and its energy requirements monitored and analyzed for one year prior to the selection of 40 Kilowatt fuel cell field testsites. Analyses in support of the selection of sites for instrumentation continued to show that many building sectors offered considerable market potential. These sectors include nursing home, health club, restaurant, industrial, hotel/motel and apartment.

Corrective Action Unit (CAU) 557 is located in Areas 1, 3, 6, and 25 of the Nevada TestSite, which is approximately 65 miles northwest of Las Vegas, Nevada, and is comprised of the four corrective action sites (CASs) listed below: • 01-25-02, Fuel Spill • 03-02-02, Area 3 Subdock UST • 06-99-10, Tar Spills • 25-25-18, Train Maintenance Bldg 3901 Spill Site These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 3, 2008, by representatives of the Nevada Division of Environmental Protection (NDEP); U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 557. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 557 includes the following activities: • Move surface debris and/or materials, as needed, to facilitate sampling. • Conduct radiological survey at CAS 25-25-18. • Perform field screening. • Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern are present. • If contaminants of concern are present, collect additional step-out samples to define the extent of the contamination. • Collect samples of investigation-derived waste, as needed, for waste management purposes.

Pressure-pulse, constant-pressure flow, and pressure-buildup tests have been performed in bedded evaporites of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) site to evaluate the hydraulic properties controlling brine flow through the Salado. Transmissivities have been interpreted from six sequences of tests conducted on five stratigraphic intervals within 15 m of the WIPP underground excavations.

Corrective Action Unit (CAU) 370 is located in Area 4 of the Nevada TestSite, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 370 is comprised of Corrective Action Site (CAS) 04-23-01, Atmospheric TestSite T-4. This site is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and/or implement a corrective action. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for this CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The investigation results may also be used to evaluate improvements in the Soils Project strategy to be implemented. The site will be investigated based on the data quality objectives (DQOs) developed on December 10, 2007, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Desert Research Institute; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 370. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to the CAS. The scope of the CAI for CAU 370 includes the following activities: • Move surface debris and/or materials, as needed, to facilitate sampling. • Conduct radiological surveys. • Perform field screening. • Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern are present. • If contaminants of concern are present, collect samples to define the extent of the contamination. • Collect samples of investigation-derived waste including debris deemed to be potential source material, as needed, for waste management purposes.

The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada TestSite locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary site risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Gnome site in southeastern New Mexico was the location of an underground detonation of a 3.5-kiloton nuclear device in 1961, and a hydrologic tracer test using radionuclides in 1963. The tracer test involved the injection of tritium, {sup 90}Sr, and {sup 137}Cs directly into the Culebra Dolomite, a nine to ten-meter-thick aquifer located approximately 150 in below land surface. The Gnome nuclear test was carried out in the Salado Formation, a thick salt deposit located 200 in below the Culebra. Because salt behaves plastically, the cavity created by the explosion is expected to close, and although there is no evidence that migration has actually occurred, it is assumed that radionuclides from the cavity are released into the overlying Culebra Dolomite during this closure process. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides may be present in concentrations exceeding drinking water regulations outside the drilling exclusion boundary established by DOE. Calculated mean tritium concentrations peak at values exceeding the U.S. Environmental Protection Agency drinking water standard of 20,000 pCi/L at distances of up to almost eight kilometers west of the nuclear test.

Act-Funded Study Assesses Contamination at Former Test Act-Funded Study Assesses Contamination at Former TestSite in California Recovery Act-Funded Study Assesses Contamination at Former TestSite in California Workers in a study funded by $38 million from the American Recovery and Reinvestment Act to assess radiological contamination have collected more than 600 soil samples and surveyed 120 acres of land for gamma radiation. Under an interagency agreement with DOE, the Environmental Protection Agency (EPA) is conducting the study at Santa Susana Field Laboratory (SSFL) Area IV and the Northern Undeveloped Land. Recovery Act-Funded Study Assesses Contamination at Former TestSite in California More Documents & Publications EA-1345: Final Environmental Assessment EIS-0402: Notice of Intent to Prepare an Environmental Impact Statement

Bechtel Nevada (BN) manages two low-level Radioactive Waste Management Sites (RWMSs) at the Nevada TestSite (NTS) for the U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NNSA/NSO). The Area 3 RWMS is located in south-central Yucca Flat and the Area 5 RWMS is located about 15 miles south, in north-central Frenchman Flat. Though located in two separate topographically closed basins, they are similar in climate and hydrogeologic setting. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste, while the Area 3 RWMS uses subsidence craters formed from underground testing of nuclear weapons for the disposal of packaged and unpackaged bulk waste. Over the next several decades, most waste disposal units at both the Area 3 and Area 5 RWMSs are anticipated to be closed. Closure of the Area 3 and Area 5 RWMSs will proceed through three phases: operational closure, final closure, and institutional control. Many waste disposal units at the Area 5RWMS are operationally closed and final closure has been placed on one unit at the Area 3 RWMS (U-3ax/bl). Because of the similarities between the two sites (e.g., type of wastes, environmental factors, operational closure cover designs, etc.), many characterization studies and data collected at the Area 3 RWMS are relevant and applicable to the Area 5 RWMS. For this reason, data and closure strategies from the Area 3 RWMS are referred to as applicable. This document is an interim Characterization Report – Operational Closure Covers, for the Area 5 RWMS. The report briefly describes the Area 5 RWMS and the physical environment where it is located, identifies the regulatory requirements, reviews the approach and schedule for closing, summarizes the monitoring programs, summarizes characterization studies and results, and then presents conclusions and recommendations.

The United States Department of Energy has prepared an Environmental Assessment (DOE/EA-1300) (EA) which analyzes the potential environmental effects of developing operating and maintaining a commercial/industrial park in Area 22 of the Nevada TestSite, between Mercury Camp and U.S. Highway 95 and east of Desert Rock Airport. The EA evaluates the potential impacts of infrastructure improvements necessary to support fill build out of the 512-acre Desert Rock Sky Park. Two alternative actions were evaluated: (1) Develop, operate and maintain a commercial/industrial park in Area 22 of the Nevada TestSite, and (2) taking no action. The purpose and need for the commercial industrial park are addressed in Section 1.0 of the EA. A detailed description of the proposed action and alternatives is in section 2.0. Section 3.0 describes the affected environment. Section 4.0 the environmental consequences of the proposed action and alternative. Cumulative effects are addressed in Section 5.0. Mitigation measures are addressed in Section 6.0. The Department of Energy determined that the proposed action of developing, operating and maintaining a commercial/industrial park in Area 22 of the Nevada TestSite would best meet the needs of the agency.

Bare Mountain comprises the isolated complex of mountain peaks southeast of the town of Beatty in southern Nye County, Nevada. This small mountain range lies between the alluvial basins of Crater Flat to the east and the northern Amargosa Desert to the southwest. The northern boundary of the range is less well defined, but for this report, the terrane of faulted Miocene volcanic rocks underlying Beatty Mountain and the unnamed hills to the east are considered to be the northernmost part of Bare Mountain. The southern tip of the mountain range is at Black Marble, the isolated hill at the southeast corner of the map. The main body of the range, between Fluorspar Canyon and Black Marble, is a folded and complexly faulted, but generally northward-dipping (or southward-dipping and northward-overturned), sequence of weakly to moderately metamorphosed upper Proterozoic and Paleozoic marine strata, mostly miogeoclinal (continental shelf) rocks. The geology of Bare Mountain is mapped at a scale of 1:24,000.

Construction of MV-6 Well Pad at the Central Nevada Test Area Construction of MV-6 Well Pad at the Central Nevada Test Area Completed Construction of MV-6 Well Pad at the Central Nevada Test Area Completed October 22, 2013 - 6:10pm Addthis What does this project do? Goal 1. Protect human health and the environment A new groundwater monitoring/validation (MV) well was installed at the Central Nevada Test Area (CNTA) in September 2013. LM proposed this well to the Nevada Division of Environmental Protection (NDEP) to enhance the existing monitoring network and to expedite the Federal Facility Agreement and Consent Order (FFACO) closure process for the CNTA Subsurface Corrective Action Unit. CNTA is located in Hot Creek Valley in Nye County, Nevada, adjacent to U.S. Highway 6, about 30 miles north of Warm Springs, Nevada. CNTA was the site of "Project Faultless," a testsite where a

Construction of MV-6 Well Pad at the Central Nevada Test Area Construction of MV-6 Well Pad at the Central Nevada Test Area Completed Construction of MV-6 Well Pad at the Central Nevada Test Area Completed October 22, 2013 - 6:10pm Addthis What does this project do? Goal 1. Protect human health and the environment A new groundwater monitoring/validation (MV) well was installed at the Central Nevada Test Area (CNTA) in September 2013. LM proposed this well to the Nevada Division of Environmental Protection (NDEP) to enhance the existing monitoring network and to expedite the Federal Facility Agreement and Consent Order (FFACO) closure process for the CNTA Subsurface Corrective Action Unit. CNTA is located in Hot Creek Valley in Nye County, Nevada, adjacent to U.S. Highway 6, about 30 miles north of Warm Springs, Nevada. CNTA was the site of "Project Faultless," a testsite where a

Of The Upper Hot Creek Ranch Geothermal Resource, Nye County, Of The Upper Hot Creek Ranch Geothermal Resource, Nye County, Nevada Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Report: Exploration Of The Upper Hot Creek Ranch Geothermal Resource, Nye County, Nevada Details Activities (2) Areas (1) Regions (0) Abstract: The Upper Hot Creek Ranch (UHCR) geothermal system had seen no significant exploration activity prior to initiation of this GRED III project. Geochemical geothermometers calculated from previously available but questionable quality analyses of the UHCR hot spring waters indicated possible subsurface temperatures of +320 oF. A complex Quaternary and Holocene faulting pattern associated with a six mile step over of the Hot Creek Range near the UHCR also indicated that this area was worthy of some

A solar sitetest module using the Rockwell AIM 65 micro-computer is described. The module is designed to work at any site where an IBM site data acquisition system (SDAS) is installed and is intended primarily as a troubleshooting tool for DOE/NASA commercial solar heating and cooling system demonstration installations. It collects sensor information (temperatures, flow rates, etc.) and displays or prints it immediately in calibrated engineering units. It will read one sensor on demand, periodically read up to 10 sensors or periodically read all sensors. Performance calculations can also be included with sensor data. Unattended operation is possible to, e.g., monitor a group of sensors once per hour. Work is underway to add a data acquisition system to the test module so that it can be used at sites which have no SDAS.

Plant mounds or blow-sand mounds are accumulations of soil particles and plant debris around large shrubs and are common features in deserts in the southwestern United States. Believed to be an important factor in their formation, the shrubs create surface roughness that causes wind-suspended particles to be deposited and resist further suspension. Shrub mounds occur in some plant communities on the Nevada TestSite, the Nevada Test and Training Range (NTTR), and Tonopah Test Range (TTR), including areas of surface soil contamination from past nuclear testing. In the 1970s as part of early studies to understand properties of actinides in the environment, the Nevada Applied Ecology Group (NAEG) examined the accumulation of isotopes of Pu, {sup 241}Am, and U in plant mounds at safety testsites. The NAEG studies found concentrations of these contaminants to be greater in shrub mounds than in the surrounding areas of desert pavement. For example, at Project 57 on the NTTR, it was estimated that 15 percent of the radionuclide inventory of the site was associated with shrub mounds, which accounted for 17 percent of the surface area of the site, a ratio of inventory to area of 0.85. At Clean Slate III at the TTR, 29 percent of the inventory was associated with approximately 32 percent of the site covered by shrub mounds, a ratio of 0.91. While the total inventory of radionuclides in intershrub areas was greater, the ratio of radionuclide inventory to area was 0.40 and 0.38, respectively, at the two sites. The comparison between the shrub mounds and adjacent desert pavement areas was made for only the top 5 cm since radionuclides at safety testsites are concentrated in the top 5 cm of intershrub areas. Not accounting for radionuclides associated with the shrub mounds would cause the inventory of contaminants and potential exposure to be underestimated. As part of its Environmental Restoration Soils Subproject, the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office has proposed that the majority of its contaminated soil 'Corrective Action Units', including the safety testsites, be closed by fencing and posting with administrative controls. The concentration of actinides in the shrub mounds has important implications for postclosure management of the safety testsites. Because resuspension factors at safety testsites can be three to four orders-of-magnitude higher than soil sites associated with atmospheric tests where criticality occurred, the shrub mounds are an important factor in stabilization of actinide contaminants. Loss of shrubs associated with mounds from fire or plant die-back from drought could cause radionuclides at these sites to become more prone to suspension and water erosion until the sites are stabilized. Alternatively, although shrub mounds are usually composed of predominantly fine sand size particles, smaller silt and clay size particles in them are often high in CaCO{sub 3} content. The CaCO{sub 3} may act as a cementing agent to limit erosion of the shrub mounds even if the vegetation cover is temporarily lost.

This report documents the results of a geologic study of the area between the underground-nuclear-explosion testing areas on Pahute Mesa, in the northwesternmost part of the Nevada TestSite, and the springs in Oasis Valley, to the west of the TestSite. The new field data described in this report are also presented in a geologic map that is a companion product(Fridrich and others, 1999) and that covers nine 7.5-minute quadrangles centered on Thirsty Canyon SW, the quadrangle in which most of the Oasis Valley springs are located. At the beginning of this study, published detailed maps were available for 3 of the 9 quadrangles of the study area: namely Thirsty Canyon (O'Connor and others, 1966); Beatty (Maldonado and Hausback, 1990); and Thirsty Canyon SE (Lipman and others, 1966). Maps of the last two of these quadrangles, however, required extensive updating owing to recent advances in understanding of the regional structure and stratigraphy. The new map data are integrated in this re port with new geophysical data for the Oasis Valley area, include gravity, aeromagnetic, and paleomagnetic data (Grauch and others, 1997; written comm., 1999; Mankinen and others, 1999; Hildenbrand and others, 1999; Hudson and others, 1994; Hudson, unpub. data).

Corrective Action Unit (CAU) 190 is located in Areas 11 and 14 of the Nevada TestSite, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 190 is comprised of the four Corrective Action Sites (CASs) listed below: (1) 11-02-01, Underground Centrifuge; (2) 11-02-02, Drain Lines and Outfall; (3) 11-59-01, Tweezer Facility Septic System; and (4) 14-23-01, LTU-6 Test Area. These sites are being investigated because existing information is insufficient on the nature and extent of potential contamination to evaluate and recommend corrective action alternatives. Additional information will be obtained before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS by conducting a corrective action investigation (CAI). The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on August 24, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture, and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 190. The scope of the CAU 190 CAI includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling; (2) Conduct radiological and geophysical surveys; (3) Perform field screening; (4) Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern (COCs) are present; (5) If COCs are present, collect additional step-out samples to define the lateral and vertical extent of the contamination; (6) Collect samples of source material, if present, to determine the potential for a release; (7) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes; and (8) Collect quality control samples. This Corrective Action Investigation Document (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) agreed to by the State of Nevada, U.S. Department of Energy, and U.S. Department of Defense. Under the FFACO, this CAIP will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval.

This Closure Report for Corrective Action Unit (CAU) 524 summarizes the disposition of four Corrective Action Sites (CAS) located in Area 25 of the Nevada TestSite, Nevada. The table listed in the report provides a description of each CAS and the status of its associated waste as listed in the ''Federal Facilities Agreement and Consent Order'' (FFACO, 1996). Copies of the Sectored Housekeeping Site Closure Verification Form for each CAS are included as Attachment A. Two of the sites required sampling for waste disposal purposes, CAS 25-22-18 and 25-22-20. The material sampled at these two sites were found to be not hazardous. Results of the sampling are included in Attachment B.

DOE is operating an environmental restoration program to characterize, remediate, and close non-Nevada TestSite locations used for nuclear testing. Evaluation of radionuclide transport by groundwater is part of preliminary risk analysis. These evaluations allow prioritization of test areas in terms of risk, provide a basis for discussions with regulators and the public about future work, and provide a framework for assessing site characterization data needs. The Rio Blanco site in Colorado was the location of the simultaneous detonation of three 30-kiloton nuclear devices. The devices were located 1780, 1899, and 2039 below ground surface in the Fort Union and Mesaverde formations. Although all the bedrock formations at the site are thought to contain water, those below the Green River Formation (below 1000 in depth) are also gas-bearing, and have very low permeabilities. The transport scenario evaluated was the migration of radionuclides from the blast-created cavity through the Fort Union Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. This modeling was performed to investigate how the uncertainty in various physical parameters affect radionuclide transport at the site, and to serve as a starting point for discussion regarding further investigation; it was not intended to be a definitive simulation of migration pathways or radionuclide concentration values. Given the sparse data, the modeling results may differ significantly from reality. Confidence in transport predictions can be increased by obtaining more site data, including the amount of radionuclides which would have been available for transport (i.e., not trapped in melt glass or vented during gas flow testing), and the hydraulic properties of the formation. 38 refs., 6 figs., 1 tab.

Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

Note: This page contains sample records for the topic "test site nye" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.

The In Situ Redox Manipulation (ISRM) experiment is being evaluated as a potential method to remove contaminants from groundwater adjacent to the Columbia River near the 100-D Area. The ISRM experiment involves using sodium dithionate (Na{sub 2}O{sub 6}S{sub 2}) to precipitate chromate from the groundwater. The treatment will likely create anoxic conditions in the groundwater down-gradient of the ISRM treatability testsite; however, the spatial extent of this anoxic plume is not exactly known. Surveys were conducted in November 1997, following the peak spawning of fall chinook salmon. Aerial surveys documented 210 redds (spawning nests) near the downstream island in locations consistent with previous surveys. Neither aerial nor underwater surveys documented fall chinook spawning in the vicinity of the ISRM treatability testsite. Based on measurements of depth, velocity, and substrate, less than 1% of the study area contained suitable fall chinook salmon spawning habitat, indicating low potential for fall chinook salmon to spawn in the vicinity of the ISRM experiment.

This Leachfield Corrective Action Units (CAUs) Work Plan has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the U.S. Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the U.S. Department of Defense (FFACO, 1996). Under the FFACO, a work plan is an optional planning document that provides information for a CAU or group of CAUs where significant commonality exists. A work plan may be developed that can be referenced by leachfield Corrective Action Investigation Plans (CAIPs) to eliminate redundant CAU documentation. This Work Plan includes FFACO-required management, technical, quality assurance (QA), health and safety, public involvement, field sampling, and waste management documentation common to several CAUs with similar site histories and characteristics, namely the leachfield systems at the Nevada TestSite (NTS) and the Tonopah Test Range (TT R). For each CAU, a CAIP will be prepared to present detailed, site-specific information regarding contaminants of potential concern (COPCs), sampling locations, and investigation methods.

The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada TestSite locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Gasbuggy site in northwestern New Mexico was the location of an underground detonation of a 29-kiloton nuclear device in 1967. The test took place in the Lewis Shale, approximately 182 m below the Ojo Alamo Sandstone, which is the aquifer closest to the detonation horizon. The conservative assumption was made that tritium was injected from the blast-created cavity into the Ojo Alamo Sandstone by the force of the explosion, via fractures created by the shot. Model results suggest that if radionuclides produced by the shot entered the Ojo Alamo, they are most likely contained within the area currently administered by DOE. The transport calculations are most sensitive to changes in the mean groundwater velocity, followed by the variance in hydraulic conductivity, the correlation scale of hydraulic conductivity, the transverse hydrodynamic dispersion coefficient, and uncertainty in the source size. This modeling was performed to investigate how the uncertainty in various physical parameters affects calculations of radionuclide transport at the Gasbuggy site, and to serve as a starting point for discussion regarding further investigation at the site; it was not intended to be a definitive simulation of migration pathways or radionuclide concentration values.

In establishing the atrium classification scheme, specific attention was given to: climate (hot-arid, warm-humid, and temperate), atrium configuration (open, closed, and adjustable tops), and thermal mechanism (natural convection, radiative cooling, shading, and others). Application of the resulting three-dimensional (three-coordinate) matrix was considered and tested. Although the testing was for purposes of checking scheme application, the procedure indicated that most of the atria examined were of the adjustable-top configuration with daylighting the principal functional mode. However, it was noted that thermally-induced air flow was present in many of the atria classified. In the identification of promising testsites it was noted that there appears to be a shortage of buildings which meet the atrium definition. Consequently, prospective testsites were categorized as follows based upon anticipated value to the study: commercial atria already constructed, commercial atria planned or under construction, and residential atria already constructed.

499 499 Radiological/Nuclear Countermeasures Test and Evaluation Complex, Nevada TestSite Final Environmental Assessment August 2004 U. S. Department of Energy National Nuclear Security Administration Nevada Site Office Las Vegas, Nevada Available for sale to the Public, in paper, from: U.S. Department of Commerce National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Phone: 800.553.6847 Fax: 703.605.6900 Email: orders@ntis..gov Online Ordering: http://www.ntis.gov/ordering.htm Available electronically at: http://www.osti.gov/bridge Available for a processing fee to U.S. Department of Energy and its contractors in paper from-- U.S. Department of Energy Office of Scientific and Technical Information

A Cleanup and Treatment (CAT) test was conducted in 1981 at Area 11, Nevada TestSite. Its purpose was to evaluate the effectiveness of using a large truck-mounted vacuum cleaner similar to those used to clean paved streets for cleaning radiological contamination from the surface of desert soils. We found that four passes with the vehicle removed 97% of the alpha contamination and reduced resuspension by 99.3 to 99.7%. Potential exposure to cleanup workers was slight when compared to natural background exposure. 7 refs., 1 fig., 2 tabs.

CAU 104 comprises the 15 CASs listed below: (1) 07-23-03, Atmospheric TestSite T-7C; (2) 07-23-04, Atmospheric TestSite T7-1; (3) 07-23-05, Atmospheric TestSite; (4) 07-23-06, Atmospheric TestSite T7-5a; (5) 07-23-07, Atmospheric TestSite - Dog (T-S); (6) 07-23-08, Atmospheric TestSite - Baker (T-S); (7) 07-23-09, Atmospheric TestSite - Charlie (T-S); (8) 07-23-10, Atmospheric TestSite - Dixie; (9) 07-23-11, Atmospheric TestSite - Dixie; (10) 07-23-12, Atmospheric TestSite - Charlie (Bus); (11) 07-23-13, Atmospheric TestSite - Baker (Buster); (12) 07-23-14, Atmospheric TestSite - Ruth; (13) 07-23-15, Atmospheric TestSite T7-4; (14) 07-23-16, Atmospheric TestSite B7-b; (15) 07-23-17, Atmospheric TestSite - Climax These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 28, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 104. The releases at CAU 104 consist of surface-deposited radionuclides from 30 atmospheric nuclear tests. The presence and nature of contamination at CAU 104 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) to the dose-based final action level (FAL). The presence of TED exceeding the FAL is considered a radiological contaminant of concern (COC). Anything identified as a COC will require corrective action. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters will be used to measure external radiological dose. Based on process knowledge of the releases associated with the nuclear tests and radiological survey information about the location and shape of the resulting contamination plume, it was determined that the releases from the nuclear tests are co-located and will be investigated concurrently. A field investigation will be performed to define areas where TED exceeds the FAL and to determine whether other COCs are present at the site. The investigation will also collect information to determine the presence and nature of contamination associated with migration and excavation, as well as any potential releases discovered during the investigation. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

. Testing and verification of the skid-mounted design should lead to adoption of this system in commercial bromide. As the vapor condenses, chilled water is produced. This advanced double-effect chiller uses two building structures at a specific site while maintaining features, which optimize system performance

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office Environmental Management Program is responsible for carrying out the disposal of on-site and off-site generated low-level radioactive waste (LLW) and low-level radioactive mixed waste (MW) at the Nevada TestSite (NTS). Core elements of this mission are ensuring safe and cost-effective disposal while protecting workers, the public, and the environment. This paper focuses on the impacts of new policies, processes, and opportunities at the NTS related to LLW and MW. Covered topics include: the first year of direct funding for NTS waste disposal operations; zero tolerance policy for non-compliant packages; the suspension of mixed waste disposal; waste acceptance changes; DOE Consolidated Audit Program (DOECAP) auditing; the 92-Acre Area closure plan; new eligibility requirements for generators; and operational successes with unusual waste streams.

Corrective Action Unit (CAU) 390 consists four Corrective Action Sites (CASs) located in Areas 9, 10, and 12 of the Nevada TestSite. The closure activities performed at the CASs include: (1) CAS 09-99-03, Wax, Paraffin: 2 cubic yards of drilling polymer was removed on June 20,2005, and transported to the Area 9 Landfill for disposal. (2) CAS 10-99-01, Epoxy Tar Spill: 2 cubic feet of asphalt waste was removed on June 20,2005, and transported to the Area 9 Landfill for disposal. (3) CAS 10-99-03, Tar Spills: 3 cubic yards of deteriorated asphalt waste was removed on June 20,2005, and transported to the Area 9 Landfill for disposal. (4) CAS 12-25-03, Oil Stains (2); Container: Approximately 16 ounces of used oil were removed from ventilation equipment on June 28,2005, and recycled. One CAS 10-22-19, Drums, Stains, was originally part of CAU 390 but was transferred out of CAU 390 and into CAU 550, Drums, Batteries, and Lead Materials. The transfer was approved by the Nevada Division of Environmental Protection on August 19,2005, and a copy of the approval letter is included in Appendix D of this report.

Pacific Northwest Laboratory (PNL), as part of the Hanford Site Ground-Water Surveillance Project, is responsible for monitoring the movement and fate of contamination within the unconfined aquifer to ensure that public health and the environment are protected. To support the monitoring and assessment of contamination migration on the Hanford Site, a sitewide 3-dimensional groundwater flow model is being developed. Providing quantitative hydrologic property data is instrumental in development of the 3-dimensional model. Multilevel monitoring facilities have been installed to provide detailed, vertically distributed hydrologic characterization information for the Hanford Site unconfined aquifer. In previous reports, vertically distributed water-level and hydrochemical data obtained over time from these multi-level monitoring facilities have been evaluated and reported. This report describes the B pond facility in Section 2.0. It also provides analysis results for a constant-rate pumping test (Section 3.0) and slug interference test (Section 4.0) that were conducted at a multilevel test facility located near B Pond (see Figure 1. 1) in the central part of the Hanford Site. A hydraulic test summary (Section 5.0) that focuses on the comparison of hydraulic property estimates obtained using the two test methods is also presented. Reference materials are listed in Section 6.0.

This Streamlined Approach for Environmental Restoration (SAFER) plan addresses the activities necessary to close Corrective Action Unit (CAU) 398: Area 25 Spill Sites. CAU 398, located in Area 25 of the Nevada TestSite, is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (FFACO, 1996), and consists of the following 13 Corrective Action Sites (CASs) (Figure 1): (1) CAS 25-44-01 , a fuel spill on soil that covers a concrete pad. The origins and use of the spill material are unknown, but the spill is suspected to be railroad bedding material. (2) CAS 25-44-02, a spill of liquid to the soil from leaking drums. (3) CAS 25-44-03, a spill of oil from two leaking drums onto a concrete pad and surrounding soil. (4) CAS 25-44-04, a spill from two tanks containing sulfuric acid and sodium hydroxide used for a water demineralization process. (5) CAS 25-25-02, a fuel or oil spill from leaking drums that were removed in 1992. (6) CAS 25-25-03, an oil spill adjacent to a tipped-over drum. The source of the drum is not listed, although it is noted that the drum was removed in 1991. (7) CAS 25-25-04, an area on the north side of the Engine-Maintenance, Assembly, and Disassembly (E-MAD) facility, where oils and cooling fluids from metal machining operations were poured directly onto the ground. (8) CAS 25-25-05, an area of oil and/or hydraulic fluid spills beneath the heavy equipment once stored there. (9) CAS 25-25-06, an area of diesel fuel staining beneath two generators that have since been removed. (10) CAS 25-25-07, an area of hydraulic oil spills associated with a tunnel-boring machine abandoned inside X-Tunnel. (11) CAS 25-25-08, an area of hydraulic fluid spills associated with a tunnel-boring machine abandoned inside Y-Tunnel. (12) CAS 25-25-16, a diesel fuel spill from an above-ground storage tank located near Building 3320 at Engine Test Stand-1 (ETS-1) that was removed in 1998. (13) CAS 25-25-17, a hydraulic oil spill associated with the historical operations of a vacuum pump oil recovery system at the E-MAD facility.

The U.S. Department of Energy (DOE) has prepared this EA to assess environmental and human health Issues and to determine potential impacts associated with the proposed Hoe Creek Underground Coal Gasification TestSite Remediation that would be performed at the Hoe Creek site in Campbell County, Wyoming. The Hoe Creek site is located south-southwest of the town of Gillette, Wyoming, and encompasses 71 acres of public land under the stewardship of the Bureau of Land Management. The proposed action identified in the EA is for the DOE to perform air sparging with bioremediation at the Hoe Creek site to remove contaminants resulting from underground coal gasification (UCG) experiments performed there by the DOE in the late 1970s. The proposed action would involve drilling additional wells at two of the UCG testsites to apply oxygen or hydrogen peroxide to the subsurface to volatilize benzene dissolved in the groundwater and enhance bioremediation of non-aqueous phase liquids present in the subsurface. Other alternatives considered are site excavation to remove contaminants, continuation of the annual pump and treat actions that have been used at the site over the last ten years to limit contaminant migration, and the no action alternative. Issues examined in detail in the EA are air quality, geology, human health and safety, noise, soils, solid and hazardous waste, threatened and endangered species, vegetation, water resources, and wildlife. Details of mitigative measures that could be used to limit any detrimental effects resulting from the proposed action or any of the alternatives are discussed, and information on anticipated effects identified by other government agencies is provided.

This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi Resource Conservation and Recovery Act Unit, located in Area 3 of the Nevada TestSite, Nye County, Nevada, during the October 1999 to October 2000 period. Inspections of the U-3fi Resource Conservation and Recovery Act Unit are conducted to determine and document the physical condition of the concrete pad, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. The objective of the neutron-logging program is to monitor the soil moisture conditions along the 128-meter (m) (420-feet [ft]) ER3-3 monitoring well and detect changes that maybe indicative of moisture movement in the regulated interval extending between 73 to 82 m (240 to 270 ft) or to detect changes that maybe indicative of subsidence within the disposal unit itself. Physical inspections of the closure were completed in March and September 2000 and indicated that the site is in good condition with no significant findings noted. The directional survey which is required to be completed every five years was run in the ER3-3 casing to determine if subsidence was occurring in the U-3fi emplacement borehole. Small changes were noted which are attributed to initial settling of the sand pack stemming. No evidence of subsidence within the emplacement borehole was observed. The subsidence survey for the October 1999 to October 2000 monitoring period indicated an increase in elevation of 0.244 centimeters (cm) (0.008 ft) compared to the previous year, July 1999. All changes in subsidence survey data taken to date are so small as to be at the survey instrument resolution level and it is not clear if they represent subsidence or measurement error. There is no clear evidence for any subsidence of the monument. Soil moisture monitoring results indicate dry stable conditions for all quarterly monitoring periods. The Residual Raw Neutron Counts remain below the compliance Action Level of 200 counts within the regulated interval of 73 to 82 m (240 to 270 ft) for the period from October 1999 through October 2000.

This Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 499: Hydrocarbon Spill Site, in accordance with the Federal Facility Agreement and Consent Order (FFACO, 1996) and the Nevada Division of Environmental Protection (NDEP)-approved Streamlined Approach for Environmental Restoration (SAFER) Plan for CAU 499: Hydrocarbon Spill Site, Tonopah Test Range (TTR), Nevada (US Department of Energy, Nevada Operations Office [DOE/NV], 2001). CAU 499 consists of one Corrective Action Site (CAS): RG-25-001-RD24: Radar 24 Diesel Spill Site which is approximately 4.0 kilometers (2.5 miles) southwest of the Area 3 Compound at the end of Avenue 24. The Hydrocarbon Spill Site is a diesel fuel release site that is assumed to have been caused by numerous small historical over-fillings, spills, and leaks from an above-ground storage tank (AST) over a period of approximately 36 years. The tank was located on the east side of Building 24-50 on the TTR.

This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for the closure of Corrective Action Unit (CAU) 121, Storage Tanks and Miscellaneous Sites. CAU 121 is currently listed in Appendix III of the ''Federal Facility Agreement and Consent Order'' (FFACO, 1996) and consists of three Corrective Action Sites (CASs) located in Area 12 of the Nevada TestSite (NTS): CAS 12-01-01, Aboveground Storage Tank; CAS 12-01-02, Aboveground Storage Tank; and CAS 12-22-26, Drums; 2 AST's. CASs 12-01-01 and 12-01-02 are located to the west of the Area 12 Camp, and CAS 12-22-26 is located near the U-12g Tunnel, also known as G-tunnel, in Area 12 (Figure 1). The aboveground storage tanks (ASTs) present at CASs 12-01-01 and 12-01-02 will be removed and disposed of at an appropriate facility. Soil below the ASTs will be sampled to identify whether it has been impacted with chemicals or radioactivity above action levels. If impacted soil above action levels is present, the soil will be excavated and disposed of at an appropriate facility. The CAS 12-22-26 site is composed of two overlapping areas, one where drums had formerly been stored, and the other where an AST was used to dispense diesel for locomotives used at G-tunnel. This area is located above an underground radioactive materials area (URMA), and within an area that may have elevated background radioactivity because of containment breaches during nuclear tests and associated tunnel reentry operations. CAS 12-22-26 does not include the URMA or the elevated background radioactivity. An AST that had previously been used to store liquid magnesium chloride (MgCl) was properly disposed of several years ago, and releases from this tank are not an environmental concern. The diesel AST will be removed and disposed of at an appropriate facility. Soil at the former drum area and the diesel AST area will be sampled to identify whether it has been impacted by releases, from the drums or the AST, with chemicals or radioactivity above action levels. CAS 12-22-26 has different potential closure pathways that are dependent upon the concentrations and chemicals detected. If only petroleum hydrocarbons are detected above action levels, then the area will be use-restricted. It will not be excavated because of the more significant hazard of excavating within a URMA. Similarly, polychlorinated biphenyls (PCBs) will only be excavated for concentrations of 50 parts per million (ppm) or greater, if there are no other factors that require excavation. For PCBs at concentrations above 1 ppm, the area will be use-restricted as required by Title 40, Code of Federal Regulations (CFR) Part 761 for PCBs (CFR, 2006), in the ''Toxic Substances Control Act'' (TSCA). Other chemicals at concentrations above the final action levels (FALs) will be excavated. If radioactivity is above action levels, then the soil will be excavated only to a depth of 1 foot (ft) below ground surface (bgs) and replaced with clean fill. This action is intended to remove the ''hot spot'' on the surface caused by leakage from a drum, and not to remediate the URMA.

The Nevada TestSite (NTS) is located in southwestern Nevada, about 105 km (65 mi) northwest of the city of Las Vegas. A series of tests was conducted in the late 1950s and early 1960s at or near the NTS to study issues involving plutonium-bearing devices. These tests resulted in the dispersal of about 5 TBq of {sup 239,24O}Pu on the surficial soils at the test locations. Additionally, underground tests of nuclear weapons devices have been conducted at the NTS since late 1962; ground water beneath the NTS has been contaminated with radionuclides produced by these tests. These two important problems have been selected for assessment. Regarding the plutonium contamination, because the residual {sup 239}Pu decays slowly (half-life of 24,110 y), these sites could represent a long-term hazard if they are not remediated and if institutional controls are lost. To investigate the magnitude of the potential health risks for this no-remediation case, three basic exposure scenarios were defined that could bring individuals in contact with {sup 239,24O}Pu at the sites: (1) a resident living in a subdivision, (2) a resident farmer, and (3) a worker at a commercial facility -- all located at a testsite. The predicted cancer risks for the resident farmer were more than a factor of three times higher than the suburban resident at the median risk level, and about a factor of ten greater than the reference worker at a commercial facility. At 100 y from the present, the 5, 50, and 95th percentile risks for the resident farmer at the most contaminated site were 4 x 10{sup {minus}6}, 6 x 10{sup {minus}5}, and 5 x 10{sup {minus}4}, respectively. For the assessment of Pu in surface soil, the principal sources of uncertainty in the estimated risks were population mobility, the relationship between indoor and outdoor contaminant levels, and the dose and risk factors for bone, liver, and lung.

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This document is part of an effort to re-evaluate all FFACO URs against the current RBCA criteria (referred to in this document as the Industrial Sites [IS] RBCA process) as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006a). After reviewing all of the existing FFACO URs, the 12 URs addressed in this Supplemental Investigation Plan (SIP) could not be evaluated against the current RBCA criteria as sufficient information about the contamination at each site was not available. This document presents the plan for conducting field investigations to obtain the needed information. This SIP includes URs from Corrective Action Units (CAUs) 326, 339, 358, 452, 454, 464, and 1010, located in Areas 2, 6, 12, 19, 25, and 29 of the Nevada TestSite, which is approximately 65 miles northwest of Las Vegas, Nevada; and CAU 403, located in Area 3 of the Tonopah Test Range, which is approximately 165 miles north of Las Vegas, Nevada.

Geologic data for ten holes drilled in areas used by Los Alamos National Laboratory at the Nevada TestSite are presented in this report. The holes include emplacement holes, instrumentation holes, and Underground Test Area wells drilled during calendar years 1991 through 1995. For each hole a stratigraphic log, a detailed lithologic log, and one or two geologic cross sections are presented, along with a supplemental data sheet containing information about the drilling operations, geology, or references. For three of the holes, graphic data summary sheets with geologic and geophysical data are provided as plates.

Following revisions to the Tri-Party Agreement for Hanford Site cleanup, which specified vitrification for Complete melter feasibility and system operability immobilization of the low-level waste (LLW) tests, select reference melter(s), and establish reference derived from retrieval and pretreatment of the radioactive LLW glass formulation that meets complete systems defense wastes stored in 177 underground tanks, commercial requirements (June 1996). Available melter technologies were tested during 1994 to 1995 as part of a multiphase program to select reference Submit conceptual design and initiate definitive design technologies for the new LLW vitrification mission.

This annual report of the Site-Directed Research and Development (SDRD) program represents the highly significant R&D accomplishments conducted during fiscal year 2010. This year was noteworthy historically, as the Nevada TestSite was renamed to the Nevada National Security Site (NNSS). This change not only recognizes how the site's mission has evolved, but also heralds a future of new challenges and opportunities for the NNSS. In many ways, since its inception in 2002, the SDRD program has helped shape that evolving mission. As we approach 2012, SDRD will also mark a milestone, having completed its first full decade of innovative R&D in support of the site and national security. The program continues to fund advanced science and technology development across traditional Department of Energy (DOE) nuclear security areas such as stockpile stewardship and non-proliferation while also supporting Department of Homeland Security (DHS) needs, and specialized work for government agencies like the Department of Defense (DoD) and others. The NNSS will also contribute technologies in the areas of treaty verification and monitoring, two areas of increasing importance to national security. Keyed to the NNSS's broadened scope, the SDRD program will continue to anticipate and advance R&D projects that will help the NNSS meet forthcoming challenges.

The purpose of this Closure Report (CR) is to provide documentation of the completed corrective action at the Test Cell A Leachfield System and to provide data confirming the corrective action. The Test Cell A Leachfield System is identified in the Federal Facility Agreement and Consent Order (FFACO) of 1996 as Corrective Action Unit (CAU) 261. Remediation of CAU 261 is required under the FFACO (1996). CAU 261 is located in Area 25 of the Nevada TestSite (NTS) which is approximately 140 kilometers (87 miles) northwest of Las Vegas, Nevada (Figure 1). CAU 261 consists of two Corrective Action Sites (CASS): CAS 25-05-01, Leachfield; and CAS 25-05-07, Acid Waste Leach Pit (AWLP) (Figures 2 and 3). Test Cell A was operated during the 1960s and 1970s to support the Nuclear Rocket Development Station. Various operations within Building 3124 at Test Cell A resulted in liquid waste releases to the Leachfield and the AWLP. The following existing site conditions were reported in the Corrective Action Decision Document (CADD) (U.S. Department of Energy, Nevada Operations Office [DOE/NV], 1999): Soil in the leachfield was found to exceed the Nevada Division of Environmental Protection (NDEP) Action Level for petroleum hydrocarbons, the U.S. Environmental Protection Agency (EPA) preliminary remediation goals for semi volatile organic compounds, and background concentrations for strontium-90; Soil below the sewer pipe and approximately 4.5 meters (m) (15 feet [ft]) downstream of the initial outfall was found to exceed background concentrations for cesium-137 and strontium-90; Sludge in the leachfield septic tank was found to exceed the NDEP Action Level for petroleum hydrocarbons and to contain americium-241, cesium-137, uranium-234, uranium-238, potassium-40, and strontium-90; No constituents of concern (COC) were identified at the AWLP. The NDEP-approved CADD (DOWNV, 1999) recommended Corrective Action Alternative 2, ''Closure of the Septic Tank and Distribution Box, Partial Excavation, and Administrative Controls.'' The corrective action was performed following the NDEP-approved Corrective Action Plan (CAP) (DOE/NV, 2000).

This US Department of Energy (DOE) Environmental Remediation Sciences Project (ERSP) was designed to test fundamental hypotheses concerning the existence and nature of indigenous microbial populations of Nevada TestSite subsurface nuclear test/detonation cavities. Now called Subsurface Biogeochemical Research (SBR), this programâ??s Exploratory Research (ER) element, which funded this research, is designed to support high risk, high potential reward projects. Here, five cavities (GASCON, CHANCELLOR, NASH, ALEMAN, and ALMENDRO) and one tunnel (U12N) were sampled using bailers or pumps. Molecular and cultivation-based techniques revealed bacterial signatures at five sites (CHANCELLOR may be lifeless). SSU rRNA gene libraries contained diverse and divergent microbial sequences affiliated with known metal- and sulfur-cycling microorganisms, organic compound degraders, microorganisms from deep mines, and bacteria involved in selenate reduction and arsenite oxidation. Close relatives of Desulforudis audaxviator, a microorganism thought to subsist in the terrestrial deep subsurface on H2 and SO42- produced by radiochemical reactions, was detected in the tunnel waters. NTS-specific media formulations were used to culture and quantify nitrate-, sulfate-, iron-reducing, fermentative, and methanogenic microorganisms. Given that redox manipulations mediated by microorganisms can impact the mobility of DOE contaminants, our results should have implications for management strategies at this and other DOE sites.

This U.S. Department of Energy (DOE) Environmental Remediation Sciences Project (ERSP) was designed to test fundamental hypotheses concerning the existence and nature of indigenous microbial populations of Nevada TestSite subsurface nuclear test/detonation cavities. Now called Subsurface Biogeochemical Research (SBR), this program’s Exploratory Research (ER) element, which funded this research, is designed to support high risk, high potential reward projects. Here, five cavities (GASCON, CHANCELLOR, NASH, ALEMAN, and ALMENDRO) and one tunnel (U12N) were sampled using bailers or pumps. Molecular and cultivation-based techniques revealed bacterial signatures at five sites (CHANCELLOR may be lifeless). SSU rRNA gene libraries contained diverse and divergent microbial sequences affiliated with known metal- and sulfur-cycling microorganisms, organic compound degraders, microorganisms from deep mines, and bacteria involved in selenate reduction and arsenite oxidation. Close relatives of Desulforudis audaxviator, a microorganism thought to subsist in the terrestrial deep subsurface on H2 and SO42- produced by radiochemical reactions, was detected in the tunnel waters. NTS-specific media formulations were used to culture and quantify nitrate-, sulfate-, iron-reducing, fermentative, and methanogenic microorganisms. Given that redox manipulations mediated by microorganisms can impact the mobility of DOE contaminants, our results should have implications for management strategies at this and other DOE sites.

This Corrective Action Plan (CAP) has been prepared for the Corrective Action Unit (CAU)261 Area 25 Test Cell A Leachfield System in accordance with the Federal Facility and Consent Order (Nevada Division of Environmental Protection [NDEP] et al., 1996). This CAP provides the methodology for implementing the approved corrective action alternative as listed in the Corrective Action Decision Document (U.S. Department of Energy, Nevada Operations Office, 1999). Investigation of CAU 261 was conducted from February through May of 1999. There were no Constituents of Concern (COCs) identified at Corrective Action Site (CAS) 25-05-07 Acid Waste Leach Pit (AWLP). COCs identified at CAS 25-05-01 included diesel-range organics and radionuclides. The following closure actions will be implemented under this plan: Because COCs were not found at CAS 25-05-07 AWLP, no action is required; Removal of septage from the septic tank (CAS 25-05-01), the distribution box and the septic tank will be filled with grout; Removal of impacted soils identified near the initial outfall area; and Upon completion of this closure activity and approval of the Closure Report by NDEP, administrative controls, use restrictions, and site postings will be used to prevent intrusive activities at the site.

This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 130: Storage Tanks, Nevada TestSite, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The corrective action sites (CASs) within CAU 130 are located within Areas 1, 7, 10, 20, 22, and 23 of the Nevada TestSite. Corrective Action Unit 130 is comprised of the following CASs: • 01-02-01, Underground Storage Tank • 07-02-01, Underground Storage Tanks • 10-02-01, Underground Storage Tank • 20-02-03, Underground Storage Tank • 20-99-05, Tar Residue • 22-02-02, Buried UST Piping • 23-02-07, Underground Storage Tank This CR provides documentation supporting the completed corrective action investigations and provides data confirming that the closure objectives for CASs within CAU 130 were met. To achieve this, the following actions were performed: • Reviewed the current site conditions, including the concentration and extent of contamination. • Implemented any corrective actions necessary to protect human health and the environment. • Properly disposed of corrective action and investigation-derived wastes. From August 4 through September 30, 2008, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for CAU 130, Storage Tanks, Nevada TestSite, Nevada. The purposes of the activities as defined during the data quality objectives process were: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, confirm that no residual contamination is present, and properly dispose of wastes. Constituents detected during the closure activities were evaluated against final action levels to identify COCs for CAU 130. Assessment of the data generated from closure activities indicates that no further action is necessary because no COCs were identified at any CAU 130 CAS. Debris removal from these CASs was considered a best management practice because no contamination was detected. The DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: • No further corrective action is required at all CAU 130 CASs. • A Notice of Completion to DOE, National Nuclear Security Administration Nevada Site Office, is requested from the Nevada Division of Environmental Protection for closure of CAU 130. • Corrective Action Unit 130 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order.

The groundwater flow system of the Nevada TestSite and surrounding region was evaluated to estimate the highest potential current and near-term risk to the public and the environment from groundwater contamination downgradient of the underground nuclear testing areas. The highest, or greatest, potential risk is estimated by assuming that several unusually rapid transport pathways as well as public and environmental exposures all occur simultaneously. These conservative assumptions may cause risks to be significantly overestimated. However, such a deliberate, conservative approach ensures that public health and environmental risks are not underestimated and allows prioritization of future work to minimize potential risks. Historical underground nuclear testing activities, particularly detonations near or below the water table, have contaminated groundwater near testing locations with radioactive and nonradioactive constituents. Tritium was selected as the contaminant of primary concern for this phase of the project because it is abundant, highly mobile, and represents the most significant contributor to the potential radiation dose to humans for the short term. It was also assumed that the predicted risk to human health and the environment from tritium exposure would reasonably represent the risk from other, less mobile radionuclides within the same time frame. Other contaminants will be investigated at a later date. Existing and newly collected hydrogeologic data were compiled for a large area of southern Nevada and California, encompassing the Nevada TestSite regional groundwater flow system. These data were used to develop numerical groundwater flow and tritium transport models for use in the prediction of tritium concentrations at hypothetical human and ecological receptor locations for a 200-year time frame. A numerical, steady-state regional groundwater flow model was developed to serve as the basis for the prediction of the movement of tritium from the underground testing areas on a regional scale. The groundwater flow model was used in conjunction with a particle-tracking code to define the pathlines followed by groundwater particles originating from 415 points associated with 253 nuclear test locations. Three of the most rapid pathlines were selected for transport simulations. These pathlines are associated with three nuclear test locations, each representing one of the three largest testing areas. These testing locations are: BOURBON on Yucca Flat, HOUSTON on Central Pahute Mesa, and TYBO on Western Pahute Mesa. One-dimensional stochastic tritium transport simulations were performed for the three pathlines using the Monte Carlo method with Latin hypercube sampling. For the BOURBON and TYBO pathlines, sources of tritium from other tests located along the same pathline were included in the simulations. Sensitivity analyses were also performed on the transport model to evaluate the uncertainties associated with the geologic model, the rates of groundwater flow, the tritium source, and the transport parameters. Tritium concentration predictions were found to be mostly sensitive to the regional geology in controlling the horizontal and vertical position of transport pathways. The simulated concentrations are also sensitive to matrix diffusion, an important mechanism governing the migration of tritium in fractured carbonate and volcanic rocks. Source term concentration uncertainty is most important near the test locations and decreases in importance as the travel distance increases. The uncertainty on groundwater flow rates is as important as that on matrix diffusion at downgradient locations. The risk assessment was performed to provide conservative and bounding estimates of the potential risks to human health and the environment from tritium in groundwater. Risk models were designed by coupling scenario-specific tritium intake with tritium dose models and cancer and genetic risk estimates using the Monte Carlo method. Estimated radiation doses received by individuals from chronic exposure to tritium, and the corre

This report provides (1) an overview of all tracer testing conducted in the Culebra Dolomite Member of the Rustler Formation at the Waste Isolation Pilot Plant (WPP) site, (2) a detailed description of the important information about the 1995-96 tracer tests and the current interpretations of the data, and (3) a summary of the knowledge gained to date through tracer testing in the Culebra. Tracer tests have been used to identify transport processes occurring within the Culebra and quantify relevant parameters for use in performance assessment of the WIPP. The data, especially those from the tests performed in 1995-96, provide valuable insight into transport processes within the Culebra. Interpretations of the tracer tests in combination with geologic information, hydraulic-test information, and laboratory studies have resulted in a greatly improved conceptual model of transport processes within the Culebra. At locations where the transmissivity of the Culebra is low ( 4 x 10{sup -6} m{sup 2}/s), we conceptualize the Culebra as a heterogeneous, layered, fractured medium in which advection occurs largely through fractures and solutes diffuse between fractures and matrix at multiple rates. The variations in diffusion rate can be attributed to both variations in fracture spacing (or the spacing of advective pathways) and matrix heterogeneity. Flow and transport appear to be concentrated in the lower Culebra. At all locations, diffusion is the dominant transport process in the portions of the matrix that tracer does not access by flow.

Measuring and Test Equipment Measuring and Test Equipment Assessment Plan NNSA/Nevada Site Office Independent Oversight Division Performance Objective: The objective of this assessment is to determine whether a program is in place which assures that Measuring and Test Equipment (M&TE) used in activities affecting quality and safety are properly controlled, calibrated, and adjusted at specified times to maintain accuracy within necessary limits. Criteria: All M&TE is uniquely identified, calibrated, controlled, and provides accuracy traceability. A recall program maintains the total inventory and status of all M&TE. Out-of-tolerance M&TE is removed from service. Plant equipment calibrated with out-of-tolerance M&TE is evaluated in a timely manner for impact on previous output, current operability and is re-

A fluidized-bed dryer was built and operated at the Raft River Geothermal TestSite in south central Idaho to test the feasibility of using low-temperature (145/sup 0/C or lower) geothermal fluids as an energy source for drying operations. The dryer performed successfully on two potato industry waste products that had a solid content of 5 to 13%. The dried product was removed as a sand-like granular material or as fines with a flour-like texture. Test results, observations, and design recommendations are presented. Also presented is an economic evaluation for commercial-scale drying plants using either geothermal low-temperature water or oil as a heat source.

Measuring and Test Equipment Measuring and Test Equipment Assessment Plan NNSA/Nevada Site Office Independent Oversight Division Performance Objective: The objective of this assessment is to determine whether a program is in place which assures that Measuring and Test Equipment (M&TE) used in activities affecting quality and safety are properly controlled, calibrated, and adjusted at specified times to maintain accuracy within necessary limits. Criteria: All M&TE is uniquely identified, calibrated, controlled, and provides accuracy traceability. A recall program maintains the total inventory and status of all M&TE. Out-of-tolerance M&TE is removed from service. Plant equipment calibrated with out-of-tolerance M&TE is evaluated in a timely manner for impact on previous output, current operability and is re-

This Facility Closure Report (FCR) has been prepared to document the actions taken to permanently close the remaining accessible areas of U12t-Tunnel (T-Tunnel) in Area 12 of the Nevada TestSite (NTS). The closure of T-Tunnel was a prerequisite to transfer facility ownership from the Defense Threat Reduction Agency (DTRA) to the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Closure of the facility was accomplished with the cooperation and concurrence of both NNSA/NSO and the Nevada Division of Environmental Protection (NDEP). The purpose of this FCR is to document that the closure of T-Tunnel complied with the closure requirements specified in the Facility Closure Plan for N- and T-Tunnels Area 12, Nevada TestSite (Appendix D) and that the facility is ready for transfer to NNSA/NSO. The Facility Closure Plan (FCP) is provided in Appendix D. T-Tunnel is located approximately 42 miles north of Mercury in Area 12 of the NTS (Figure 1). Between 1970 and 1987, T-Tunnel was used for six Nuclear Weapons Effects Tests (NWETs). The tunnel was excavated horizontally into the volcanic tuffs of Rainier Mesa. The T-Tunnel complex consists of a main access drift with two NWET containment structures, a Gas Seal Plug (GSP), and a Gas Seal Door (GSD) (Figure 2). The T-Tunnel complex was mothballed in 1993 to preserve the tunnel for resumption of testing, should it happen in the future, to stop the discharge of tunnel effluent, and to prevent unauthorized access. This was accomplished by sealing the main drift GSD.

This Closure Report (CR) has been prepared for the Area 25 Contaminated Waste Dumps (CWD), Corrective Action Unit (CAU) 143 in accordance with the Federal Facility Agreement and Consent Order [FFACO] (FFACO, 1996) and the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) for CAU 143: Area 25, Contaminated Waste Dumps, Nevada TestSite, Nevada. CAU 143 consists of two Corrective Action Sites (CASs): 25-23-09 CWD No.1, and 25-23-03 CWD No.2. The Area 25 CWDs are historic disposal units within the Area 25 Reactor Maintenance, Assembly, and Disassembly (R-MAD), and Engine Maintenance, Assembly, and Disassembly (E-MAD) compounds located on the Nevada TestSite (NTS). The R-MAD and E-MAD facilities originally supported a portion of the Nuclear Rocket Development Station in Area 25 of the NTS. CWD No.1 CAS 25-23-09 received solid radioactive waste from the R-MAD Compound (East Trestle and West Trench Berms) and 25-23-03 CWD No.2 received solid radioactive waste from the E-MAD Compound (E-MAD Trench).

In February and March 2012, a tracer test involving the injection of a radionuclide-colloid cocktail was conducted in the MI shear zone at the Grimsel TestSite, Switzerland, as part of the Colloids Formation and Migration (CFM) project. The colloids were derived from FEBEX bentonite, which is mined in Spain and is being considered as a potential waste package backfill in a Spanish nuclear waste repository. The tracer test, designated test 12-02 (second test in 2012), involved the injection of the tracer cocktail into borehole CFM 06.002i2 and extraction from the Pinkel surface packer at the main access tunnel wall approximately 6.1 m from the injection interval. The test configuration is depicted in Figure 1. This configuration has been used in several conservative tracer tests and two colloid-homologue tracer tests since 2007, and it is will be employed in an upcoming test involving the emplacement of a radionuclide-doped bentonite plug into CFM 06.002i2 to evaluate the swelling and erosion of the bentonite and the transport of bentonite colloids and radionuclides from the source to the extraction point at the tunnel wall. Interpretive analyses of several of the previous tracer tests, from 09-01 through 12-02 were provided in two previous Used Fuel Disposition Program milestone reports (Arnold et al., 2011; Kersting et al., 2012). However, only the data for the conservative tracer Amino-G Acid was previously analyzed from test 12-02 because the other tracer data from this test were not available at the time. This report documents the first attempt to quantitatively analyze the radionuclide and colloid breakthrough curves from CFM test 12-02. This report was originally intended to also include an experimental assessment of colloid-facilitated transport of uranium by bentonite colloids in the Grimsel system, but this assessment was not conducted because it was reported by German collaborators at the Karlsruhe Institute of Technology (KIT) that neither uranium nor neptunium adsorbed appreciably to FEBEX bentonite colloids in Grimsel groundwater (Huber et al., 2011). The Grimsel groundwater has a relatively high pH of {approx}9, so the lack of uranium and neptunium adsorption to clay is not surprising given the tendency for these actinides to form very stable negative or neutrally-charged uranyl- or calcium-uranyl-carbonate complexes at these pH, particularly in a water that is effectively saturated with respect to calcite. It was also observed in testing conducted at LANL earlier in 2012 that uranium did not adsorb measurably to Grimsel granodiorite in a synthetic Grimsel groundwater at pH {approx}8.5 (Kersting et al., 2012). Thus, the planned experimental work was not pursued because all the available information clearly pointed to an expected result that uranium transport would not be facilitated by clay colloids in the Grimsel system.

A proof-of-principle test is underway near the Hanford Site 241-SX Tank Farm. The test will evaluate a potential remediation technology that will use tank farm-deployable equipment to remove contaminated pore water from vadose zone soils. The test system was designed and built to address the constraints of working within a tank farm. Due to radioactive soil contamination and limitations in drilling near tanks, small-diameter direct push drilling techniques applicable to tank farms are being utilized for well placement. To address space and weight limitations in working around tanks and obstacles within tank farms, the aboveground portions of the test system have been constructed to allow deployment flexibility. The test system utilizes low vacuum over a sealed well screen to establish flow into an extraction well. Extracted pore water is collected in a well sump,and then pumped to the surface using a small-diameter bladder pump.If pore water extraction using this system can be successfully demonstrated, it may be possible to target local contamination in the vadose zone around underground storage tanks. It is anticipated that the results of this proof-of-principle test will support future decision making regarding interim and final actions for soil contamination within the tank farms.

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As part of the proficiency training for the Radiological Mapping mission of the Aerial Measuring System (AMS), a survey team from the Remote Sensing Laboratory-Nellis (RSL-Nellis) conducted an aerial radiological survey of selected areas of Area 18 of the Nevada TestSite (NTS) for the purpose of mapping man-made radiation deposited as a result of the Johnnie Boy and Little Feller I tests. The survey area centered over the Johnnie Boy ground zero but also included the ground zero and deposition area of the Little Feller I test, approximately 7,000 feet (2133 meters) southeast of the Johnnie Boy site. The survey was conducted in one flight. The completed survey covered a total of 4.0 square miles. The flight lines (with the turns) over the surveyed areas are presented in Figure 1. One 2.5-hour-long flight was performed at an altitude of 100 ft above ground level (AGL) with 200 foot flight-line spacing. A test-line flight was conducted near the Desert Rock Airstrip to ensure quality control of the data. The test line is not shown in Figure 1. However, Figure 1 does include the flight lines for a ''perimeter'' flight. The path traced by the helicopter flying over distinct roads within the survey area can be used to overlay the survey data on a base map or image. The flight survey lines were flown in an east-west orientation perpendicular to the deposition patterns for both sites. This technique provides better spatial resolution when contouring the data. The data were collected by the AMS data acquisition system (REDAR V) using an array of twelve 2-inch x 4-inch x 16-inch sodium iodide (NaI) detectors flown on-board a twin-engine Bell 412 helicopter. Data, in the form of gamma energy spectra, were collected every second over the course of the survey and were geo-referenced using a differential Global Positioning System. Spectral data allows the system to distinguish between ordinary fluctuations in natural background radiation levels and the signature produced by man-made radioisotopes. Spectral data can also identify specific radioactive isotopes. Based on the results of the RSL NTS 1994 surveys, this area was chosen for a resurvey to improve the spatial resolution of the reported depositions for the Johnnie Boy and Little Feller I events. In addition, the survey was expected to confirm the absence of detectable concentrations of Americium-241 (Am-241) at the Johnnie Boy site and attempt to confirm the presence of Uranium-235 (U-235).

Final Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada DOE/EIS-0250 Errata Sheet Since release of the Final EIS for Yucca Mountain on February 14, 2002 as part of the Site Recommendation documentation required under the Nuclear Waste Policy Act, as amended, the Department of Energy (DOE) has identified a variety of errors in the document. These errors were found to include: editing errors - errors in editorial style, rounding, and unit conversions data entry errors, errors in typing a number transcription errors - errors in transcribing information from one part of the document to another, failures to update the text from the most current analyses at the time of the

Corrective Action Unit (CAU) 563 is identified in the Federal Facility Agreement and Consent Order (FFACO) as “Septic Systems” and consists of the following four Corrective Action Sites (CASs), located in Areas 3 and 12 of the Nevada TestSite: · CAS 03-04-02, Area 3 Subdock Septic Tank · CAS 03-59-05, Area 3 Subdock Cesspool · CAS 12-59-01, Drilling/Welding Shop Septic Tanks · CAS 12-60-01, Drilling/Welding Shop Outfalls Closure activities were conducted from September to November 2009 in accordance with the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 563. The corrective action alternatives included No Further Action and Clean Closure.

The steam cleaning effluent ponds (SCEP) waste unit is located in Area 6 at the Nevada TestSite (NTS). Nevada Operations Office operates the NTS and has entered into a trilateral agreement with the State of Nevada and the Defense Special Weapons Agency (DSWA). The trilateral agreement provides a framework for identifying, characterizing, remediating, and closing environmental sites on the NTS and associated bombing ranges. The SCEP waste unit consists of: two steam cleaning effluent ponds; layout pad and associated grease trap; Building 6-623 steam cleaning pad; test pad; Building 6-623 grease trap; Building 6-800 steam cleaning pad; Building 6-800 separator; Building 6-621 sump; and the concrete asbestos piping connecting these components to both SCEPs. Clean closure is the recommended closure strategy for the majority of the components within this CAU. Four components of the unit (Building 6-621 Sump, Test Pad Grease Trap, Building 6-623 Steam Cleaning Pad, and North SCEP pipeline) are recommended to be closed in place. This closure plan provides the strategy and backup information necessary to support the clean closure of each of the individual components within CAU 93. Analytical data generated during the characterization field work and earlier sampling events indicates the majority of CAU 93 soil and infrastructure is non-hazardous (i.e., impacted primarily with petroleum hydrocarbons).

This volume includes six reports of monitoring work to determine the status of and trends in flora and fauna populations on the Nevada TestSite (NTS) from 1989 through 1991. The Nevada Operations Office of the US Department of Energy supported monitoring under its Basic Environmental Compliance and Monitoring Program (BECAMP) since 1987. Under this program several undisturbed baseline plots, and numerous plots in disturbed areas, are sampled on annual or three-year cycles. Perennial plant populations, ephemeral plants, small mammals, reptiles, birds, and large mammals were monitored. Monitoring results are reported for five baseline sites, one from each major landform on the NTS (Jackass Flats, Frenchman Flat, Yucca Flat, Pahute Mesa, and Rainier Mesa), and for areas cleared of vegetation by fires, atmospheric nuclear weapons tests, construction, and gophers. Roadside flora and fauna were studied at two locations, and several historical study plots around the NTS were recensused to determine vegetation changes over long time spans. Three subsidence craters resulting from below-ground nuclear weapons tests were also studied. A major influence on plants and animals during the report period was a severe drought during 1989 and 1990, followed by more moderate drought in 1991.

This Closure Report documents the closure activities conducted for CAU 387: Spill Sites and Releases. Closure activities were performed in two phases. Phase I activities consisted of collecting waste characterization samples of soil at appropriate sites. The results were used to determine how waste generated during closure activities would be handled and disposed (i.e., as nonhazardous sanitary or hazardous waste). Phase 2 activities consisted of closing each CAS by removing debris and/or soil, disposing of the generated waste, and verifying that each site was clean-closed by visual inspection and/or collecting soil verification samples for laboratory analysis. Additionally, seven sites were closed with no further action after concurrence with Nevada Division of Environmental Protection (NDEP). Four other sites were moved into different CAUs in Appendix III of the FFACO because the housekeeping process was not adequate to close them. Copies of the analytical results for the site verification samples are included in Appendix A. Copies of the Sectored Housekeeping Site Closure Verification Forms for each of the 16 CAS are included in Appendix B.

This Closure Report (CR) describes the activities performed to close CAU 115, Area 25 Test Cell A Facility, as presented in the NDEP-approved SAFER Plan (NNSA/NSO, 2004). The SAFER Plan includes a summary of the site history, process knowledge, and closure standards. This CR provides a summary of the completed closure activities, documentation of waste disposal, and analytical and radiological data to confirm that the remediation goals were met and to document final site conditions. The approved closure alternative as presented in the SAFER Plan for CAU 115 (NNSA/NSO, 2004) was clean closure; however, closure in place was implemented under a Record of Technical Change (ROTC) to the SAFER Plan when radiological surveys indicated that the concrete reactor pad was radiologically activated and could not be decontaminated to meet free release levels. The ROTC is included as Appendix G of this report. The objectives of closure were to remove any trapped residual liquids and gases, dispose regulated and hazardous waste, decontaminate removable radiological contamination, demolish and dispose aboveground structures, remove the dewar as a best management practice (BMP), and characterize and restrict access to all remaining radiological contamination. Radiological contaminants of concern (COCs) included cobalt-60, cesium-137, strontium-90, uranium-234/235/236/238, and plutonium-239/240. Additional COCs included Resource Conservation and Recovery Act (RCRA) metals, polychlorinated biphenyls (PCBs), and asbestos.

Corrective Action Unit (CAU) 543: Liquid Disposal Units is listed in Appendix III of the ''Federal Facility Agreement and Consent Order'' (FFACO) which was agreed to by the state of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense (FFACO, 1996). CAU 543 sites are located in Areas 6 and 15 of the Nevada TestSite (NTS), which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 543 consists of the following seven Corrective Action Sites (CASs) (Figure 1): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; and CAS 15-23-03, Contaminated Sump, Piping. All Area 15 CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm, which operated from 1963 to 1981 and was used to support animal experiments involving the uptake of radionuclides. Each of the Area 15 CASs, except CAS 15-23-01, is associated with the disposal of waste effluent from Building 15-06, which was the primary location of the various tests and experiments conducted onsite. Waste effluent disposal from Building 15-06 involved piping, sumps, outfalls, a septic tank with leachfield, underground storage tanks, and an aboveground storage tank (AST). CAS 15-23-01 was associated with decontamination activities of farm equipment potentially contaminated with radiological constituents, pesticides, and herbicides. While the building structures were removed before the investigation took place, all the original tanks, sumps, piping, and concrete building pads remain in place. The Area 6 CAS is located at the Decontamination Facility in Area 6, a facility which operated from 1971 to 2001 and was used to decontaminate vehicles, equipment, clothing, and other materials that had become contaminated during nuclear testing activities. The CAS includes the effluent collection and distribution systems for Buildings 6-605, 6-606, and 6-607, which consists of septic tanks, sumps, piping, floor drains, drain trenches, cleanouts, and a concrete foundation. Additional details of the site history are provided in the CAU 543 Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2004a), and the CAU 543 Corrective Action Decision Document (CADD) (NNSA/NSO, 2005).

Three conservative tracer tests have been conducted through the Bridge Fault fracture zone at the Raft River Geothermal (RRG) site. All three tests were conducted between injection well RRG-5 and production wells RRG-1 (790 m distance) and RRG-4 (740 m distance). The injection well is used during the summer months to provide pressure support to the production wells. The first test was conducted in 2008 using 136 kg of fluorescein tracer. Two additional tracers were injected in 2010. The first 2010 tracer injected was 100 kg fluorescein disodium hydrate salt on June, 21. The second tracer (100 kg 2,6-naphthalene disulfonic acid sodium salt) was injected one month later on July 21. Sampling of the two productions wells is still being performed to obtain the tail end of the second 2010 tracer test. Tracer concentrations were measured using HPLC with a fluorescence detector. Results for the 2008 test, suggest 80% tracer recover at the two production wells. Of the tracer recovered, 85% of tracer mass was recovered in well RRG-4 indicating a greater flow pathway connection between injection well and RRG-4 than RRG-1. Fluorescein tracer results appear to be similar between the 2008 and 2010 tests for well RRG-4 with peak concentrations arriving approximately 20 days after injection despite the differences between the injection rates for the two tests (~950 gpm to 475 gpm) between the 2008 and 2010. The two 2010 tracer tests will be compared to determine if the results support the hypothesis that rock contraction along the flow pathway due to the 55 oC cooler water injection alters the flow through the ~140 oC reservoir.

The underground storage tank (UST) release site 23-111-1 is located in Mercury, Nevada. The site is in Area 23 of the Nevada TestSite, (NTS) located on the north side of Building 111. The tank associated with the release was closed in place using cement grout on September 6, 1990. The tank was not closed by removal due to numerous active underground utilities, a high-voltage transformer pad, and overhead power lines. Soil samples collected below the tank bottom at the time of tank closure activities exceeded the Nevada Administrative Code Action Level of 100 milligrams per kilogram (mg/kg) for petroleum hydrocarbons. Maximum concentrations detected were 119 mg/kg. Two passive venting wells were subsequently installed at the tank ends to monitor the progress of biodegradation at the site. Quarterly air sampling from the wells was completed for approximately one year, but was discontinued since data indicated that considerable biodegradation was not occurring at the site.

For a variety of reasons, thousands of oil and gas wells have been abandoned in the Gulf Coast Region of the United States. Many of these wells penetrated geopressured zones whose resource potential for power generation was undervalued or ignored. The U.S. Department of Energy (DOE) Geopressured-Geothermal Research Program was chartered to improve geothermal technology to the point where electricity could be commercially produced from a substantial number of geopressured resource sites. This research program focused on relatively narrow technical issues that are unique to geopressured resources such as the ability to predict reservoir production capacity based on preliminary flow tests. Three well sites were selected for the research program. These are the Willis Hulin and Gladys McCall sites in Louisiana, and the Pleasant Bayou site in Texas. The final phase of this research project consists of plug and abandonment (P&A) of the wells and site restoration.

Using the transient method, we determine the permeability of high-quartz Eleana argillite from the Nevada TestSite as a function of effective pressure. By comparing calculated and observed pressure decay in the upstream reservoir, we have determined the permeability of intact and fractured specimens at effective pressures ranging from 1.0 to 24.0 MPa. Over this pressure range, Eleana argillite has a low permeability (10{sup -16} to 10{sup -19} cm{sup 2}) when intact and a higher permeability (10{sup -12} to 10{sup -17} cm{sup 2}) with one induced through-going fracture.

Sandia Corporation (a subsidiary of Lockheed Martin Corporation through its contract with the U.S. Department of Energy [DOE]), National Nuclear Security Administration (NNSA) operates the Tonopah Test Range (TTR) in Nevada. Westinghouse Government Service, TTR's operations and maintenance contractor, performs most all environmental program functions. This Annual Site Environmental Report (ASER), which is published to inform the public about environmental conditions at TTR, describes environmental protection programs and summarizes the compliance status with major environmental laws and regulations during Calendar Year (CY) 2001.

AUDIT OF SUBSIDIZED ANCILLARY SERVICES AT THE NEVADA TESTSITE The Office of Inspector General wants to make the distribution of its reports as customer friendly and cost effective as possible. Therefore, this report will be available electronically through the Internet five to seven days after publication at the following alternative addresses: Department of Energy Headquarters Gopher gopher.hr.doe.gov Department of Energy Headquarters Anonymous FTP vm1.hqadmin.doe.gov U. S. Department of Energy Human Resources and Administration Home Page http://www.hr.doe.gov/refshelf.html Your comments would be appreciated and can be provided on the Customer Response Form attached to the report.

Testing of perfluorocarbon gas tracers (PFT) on a subsurface barrier with known flaws was conducted at the Waldo TestSite operated by Science and Engineering Associates, Inc (SEA). The tests involved the use of five unique PFTs with a different tracer injected along the interior of each wall of the barrier. A fifth tracer was injected exterior to the barrier to examine the validity of diffusion controlled transport of the PFTs. The PFTs were injected for three days at a nominal flow rate of 15 cm{sup 3}/min and concentrations in the range of a few hundred ppm. Approximately 65 liters of air laced with tracer was injected for each tracer. The tracers were able to accurately detect the presence of the engineered flaws. Two flaws were detected on the north and east walls, and one flaw was detected on the south and west walls. In addition, one non-engineered flaw at the seam between the north and east walls was also detected. The use of multiple tracers provided independent confirmation of the flaws and permitted a distinction between tracers arriving at a monitoring port after being released from a nearby flaw and non-engineered flaws. The PFTs detected the smallest flaw, 0.5 inches in diameter. Visual inspection of the data showed excellent agreement with the known flaw locations and the relative size of the flaws was accurately estimated. Simultaneous with the PFT tests, SEA conducted tests with another gas tracer sulfur hexafluoride (SF{sub 6}).

This Closure Report (CR) documents the activities undertaken to close Corrective Action Unit (CAU) 326, Areas 6 and 27 Release Sites, in accordance with the Federal Facility Agreement and Consent Order (FFACO) of 1996. Site closure was performed in accordance with the Nevada Division of Environmental Protection (NDEP)-approved Streamlined Approach for Environmental Restoration Plan (SAFER) Plan for CAU 326 (US Department of Energy, Nevada Operations Office [DOE/NV, 2001]). CAU 326 consists of four Corrective Action Sites (CASs), 06-25-01, 06-25-02, 06-25-04, and 27-25-01. CAS 06-25-01 is a release site associated with an underground pipeline that carried heating oil from the heating oil underground storage tank (UST), Tank 6-CP-1, located to the west of Building CP-70 to the boiler in Building CP-1 located in the Area 6 Control Point (CP) compound. This site was closed in place administratively by implementing use restrictions. CAS 06-25-02 is a hydrocarbon release associated with an active heating oil UST, Tank 6-DAF-5, located west of Building 500 at the Area 6 Device Assembly Facility. This site was closed in place administratively by implementing use restrictions. CAS 06-25-04 was a hydrocarbon release associated with Tank 6-619-4. This site was successfully remediated when Tank 6-619-4 was removed. No further action was taken at this site. CAS 27-25-01 is an excavation that was created in an attempt to remove hydrocarbon-impacted soil from the Site Maintenance Yard in Area 27. Approximately 53 cubic meters (m{sup 3}) (70 cubic yards [yd{sup 3}]) of soil impacted by total petroleum hydrocarbons (TPH) and polychlorinated biphenyls (PCBs) was excavated from the site in August of 1994. Clean closure of this site was completed in 2002 by the excavation and disposal of approximately 160 m{sup 3} (210 yd{sup 3}) of PCB-impacted soil.

This report describes radiological survey, decontamination and decommissioning of the Nevada TestSite (NTS) Area 25 facilities and land areas incorporated in the Nuclear Rocket Development Station (NRDS). Buildings, facilities and support systems used after 1959 for nuclear reactor and engine testing were surveyed for the presence of radioactive contamination. The cleanup was part of the Surplus Facilities Management Program funded by the Department of Energy's Richland Operations Office. The radiological survey portion of the project encompassed portable instrument surveys and removable contamination surveys (swipe) for alpha and beta plus gamma radiation contamination of facilities, equipment and land areas. Soil sampling was also accomplished. The majority of Area 25 facilities and land areas have been returned to unrestricted use. Remaining radiologically contaminated areas are posted with warning signs and barricades. 12 figures.

This report provides (1) an overview of all tracer testing conducted in the Culebra Dolomite Member of the Rustler Formation at the Waste Isolation Pilot Plant (WPP) site, (2) a detailed description of the important information about the 1995-96 tracer tests and the current interpretations of the data, and (3) a summary of the knowledge gained to date through tracer testing in the Culebra. Tracer tests have been used to identify transport processes occurring within the Culebra and quantify relevant parameters for use in performance assessment of the WIPP. The data, especially those from the tests performed in 1995-96, provide valuable insight into transport processes within the Culebra. Interpretations of the tracer tests in combination with geologic information, hydraulic-test information, and laboratory studies have resulted in a greatly improved conceptual model of transport processes within the Culebra. At locations where the transmissivity of the Culebra is low (< 4 x 10{sup -6} m{sup 2}/s), we conceptualize the Culebra as a single-porosity medium in which advection occurs largely through the primary porosity of the dolomite matrix. At locations where the transmissivity of the Culebra is high (> 4 x 10{sup -6} m{sup 2}/s), we conceptualize the Culebra as a heterogeneous, layered, fractured medium in which advection occurs largely through fractures and solutes diffuse between fractures and matrix at multiple rates. The variations in diffusion rate can be attributed to both variations in fracture spacing (or the spacing of advective pathways) and matrix heterogeneity. Flow and transport appear to be concentrated in the lower Culebra. At all locations, diffusion is the dominant transport process in the portions of the matrix that tracer does not access by flow.

This Closure Report (CR) documents closure activities for Corrective Action Unit (CAU) 543, Liquid Disposal Units, according to the Federal Facility Agreement and Consent Order (FFACO, 1996) and the Corrective Action Plan (CAP) for CAU 543 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2007). CAU 543 is located at the Nevada TestSite (NTS), Nevada (Figure 1), and consists of the following seven Corrective Action Sites (CASs): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; CAS 15-23-03, Contaminated Sump, Piping; and CAS 06-07-01 is located at the Decontamination Facility in Area 6, adjacent to Yucca Lake. The remaining CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm in Area 15. The purpose of this CR is to provide a summary of the completed closure activities, to document waste disposal, and to present analytical data confirming that the remediation goals were met. The closure alternatives consisted of closure in place for two of the CASs, and no further action with implementation of best management practices (BMPs) for the remaining five CASs.

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The West Valley Demonstration Project (WVDP) has successfully pretreated and vitrified nearly all of the 600,000 gallons of liquid high-level radioactive waste that was generated at the site of the only commercial nuclear fuel reprocessing plant to have operated in the United States. Low-level waste (LLW) generated during the course of the cleanup effort now requires disposal. Currently the WVDP only ships Class A LLW for off-site disposal. It has been shipping Class A wastes to Envirocare of Utah, Inc. since 1997. However, the WVDP may also have a future need to ship Class B and Class C waste, which Envirocare is not currently authorized to accept. The Nevada TestSite (NTS), a U.S. Department of Energy (DOE) facility, can accept all three waste classifications. The WVDP set a goal to receive certification to begin shipping Class A wastes to NTS by 2001. Formal certification/approval was granted by the DOE Nevada Operations Office on July 12, 2001. This paper discusses how the WVDP contractor, West Valley Nuclear Services Company (WVNSCO), completed the activities required to achieve NTS certification in 2001 to ship waste to its facility. The information and lessons learned provided are significant because the WVDP is the only new generator receiving certification based on an NTS audit in January 2001 that resulted in no findings and only two observations--a rating that is unparalleled in the DOE Complex.

U-20c is the site of a large below-water-table nuclear test near the Nevada TestSite boundary. A conceptual model of potential groundwater migration of tritium from U-20c is constructed and quantitatively evaluated in this report. The lower portion of the collapse chimney at Benham is expected to intersect 200 m of permeable rhyolite lava, overlain by similar thicknesses of low-permeability zeolitized bedded tuff, then permeable welded tuff. Vertical groundwater flow through the chimney is predicted to be minimal, horizontal transport should be controlled by the regional groundwater flow. Analytic solutions treating only advective transport indicate 1 to 2 km of tritium movement (95% confidence interval 0.7--2.5 km) within 5 years after test-related pressure-temperature transients have dissipated. This point lies at the axis of a potentiometric surface trough along the west edge of Area 20, Nevada TestSite. Within 25 years, movement is predicted to extend to 3 km (95% confidence interval 2--5 km) approximately to the intersection of the trough and the Nevada TestSite boundary. Considering the effects of radioactive decay, but not dispersion, plume concentration would fall below Safe Drinking Water Act standards by 204 years, at a predicted distance of 11 km (95% confidence interval 7--31 km). This point is located in the eastern portion of the Timber Mountain Caldera moat within the Nellis Air Force Range (military bombing range).

CAU 570 comprises the following six corrective action sites (CASs): • 02-23-07, Atmospheric TestSite - Tesla • 09-23-10, Atmospheric TestSite T-9 • 09-23-11, Atmospheric TestSite S-9G • 09-23-14, Atmospheric TestSite - Rushmore • 09-23-15, Eagle Contamination Area • 09-99-01, Atmospheric TestSite B-9A These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 30, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 570. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The presence and nature of contamination at CAU 570 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose at sample locations to the dose-based final action level. The total effective dose will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed near the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

Under the Comprehensive Nuclear-Test-Ban Treaty (CTBT), a verification regime that includes the ability to conduct an On-Site Inspection (OSI) will be established. The Treaty allows for an OSI to include many techniques, including the radionuclide techniques of gamma radiation surveying and spectrometry and environmental sampling and analysis. Such radioactivity detection techniques can provide the “smoking gun” evidence that a nuclear test has occurred through the detection and quantification of indicative recent fission products. An OSI faces restrictions in time and manpower, as dictated by the Treaty; not to mention possible logistics difficulties due to the location and climate of the suspected explosion site. It is thus necessary to have a good understanding of the possible source term an OSI will encounter and the proper techniques that will be necessary for an effective OSI regime. One of the challenges during an OSI is to locate radioactive debris that has escaped an underground nuclear explosion (UNE) and settled on the surface near and downwind of ground zero. To support the understanding and selection of sampling and survey techniques for use in an OSI, we are currently designing an experiment, the Particulate Release Experiment (PRex), to simulate a small-scale vent from an underground nuclear explosion. PRex will occur at the Nevada National Security Site (NNSS). The project is conducted under the National Center for Nuclear Security (NCNS) funded by the National Nuclear Security Agency (NNSA). Prior to the release experiment, scheduled for Spring of 2013, the project scheduled a number of activities at the NNSS to prepare for the release experiment as well as to utilize the nuclear testing past of the NNSS for the development of OSI techniques for CTBT. One such activity—the focus of this report—was a survey and sampling campaign at the site of an old UNE that vented: DILUTED WATERS. Activities at DILUTED WATERS included vehicle-based survey, in situ measurements with high-purity germanium (HPGe) and hand-held LaBr3 systems, soil sampling with a variety of tools, and laboratory gamma spectrometric analysis of those samples. A further benefit of the measurement campaign was to gain familiarity with the many logistical aspects of performing radiological field work at NNSS ahead of the PRex. Many practical lessons concerning the proper methodologies and logistics of using the surveying and sampling equipment were noted. These Lessons Learned are compiled together in Appendix A. The vehicle-based survey was successful in that it found a previously unknown hotspot (determined to be 232Th) while it demonstrated that a better method for keeping a serpentine track without staking was needed. Some of the soil sampling equipment was found to be impractical for the application, though core sampling would not be the correct way to take soil samples for a fresh vent deposit (as opposed to an old site like DILUTED WATERS). Due to the site’s age, 137Cs was the only fission radioisotope identified, though others were searched for. While not enough samples were taken and analyzed to definitively link the 137Cs to DILUTED WATERS as opposed to other NNSS activities, results were consistent with the historical DILUTED WATERS plume. MDAs were compared for soil sampling and in situ measurements.

Postshot drilling provided essential data on the results of the underground nuclear tests conducted at the Nevada TestSite (NTS), now identified as the Nevada National Security Site (NNSS). It was the means by which samples from the zone of interest were obtained for radiochemical analysis. This handbook describes how Lawrence Livermore National Laboratory (LLNL) conducted postshot drilling operations at the NTS, and it provides a general understanding of the process. Postshot drilling is a specialized application of rotary drilling. Accordingly, this handbook gives a brief description of rotary drilling in Section 2 to acquaint the reader with the general subject before proceeding to the specialized techniques used in postshot drilling. In Section 3, the handbook describes the typical postshot drilling situation at the former NTS and the drilling methods used. Section 4 describes the typical sequence of operations in postshot drilling at the former NTS. Detailed information on special equipment and techniques is given in a series of appendices (A through F) at the end of the handbook.

A laboratory testing program was developed to examine the mechanical behavior of salt from the Richton salt dome. The resulting information is intended for use in design and evaluation of a proposed Strategic Petroleum Reserve storage facility in that dome. Core obtained from the drill hole MRIG-9 was obtained from the Texas Bureau of Economic Geology. Mechanical properties testing included: (1) acoustic velocity wave measurements; (2) indirect tensile strength tests; (3) unconfined compressive strength tests; (4) ambient temperature quasi-static triaxial compression tests to evaluate dilational stress states at confining pressures of 725, 1450, 2175, and 2900 psi; and (5) confined triaxial creep experiments to evaluate the time-dependent behavior of the salt at axial stress differences of 4000 psi, 3500 psi, 3000 psi, 2175 psi and 2000 psi at 55 C and 4000 psi at 35 C, all at a constant confining pressure of 4000 psi. All comments, inferences, discussions of the Richton characterization and analysis are caveated by the small number of tests. Additional core and testing from a deeper well located at the proposed site is planned. The Richton rock salt is generally inhomogeneous as expressed by the density and velocity measurements with depth. In fact, we treated the salt as two populations, one clean and relatively pure (> 98% halite), the other salt with abundant (at times) anhydrite. The density has been related to the insoluble content. The limited mechanical testing completed has allowed us to conclude that the dilatational criteria are distinct for the halite-rich and other salts, and that the dilation criteria are pressure dependent. The indirect tensile strengths and unconfined compressive strengths determined are consistently lower than other coastal domal salts. The steady-state-only creep model being developed suggests that Richton salt is intermediate in creep resistance when compared to other domal and bedded salts. The results of the study provide only limited information for structural modeling needed to evaluate the integrity and safety of the proposed cavern field. This study should be augmented with more extensive testing. This report documents a series of test methods, philosophies, and empirical relationships, etc., that are used to define and extend our understanding of the mechanical behavior of the Richton salt. This understanding could be used in conjunction with planned further studies or on its own for initial assessments.

The Clemson Environmental Technologies Laboratory (CETL) was contracted by the National Energy Technology Center to evaluate technologies that might be used to reduce the volume of plutonium-contaminated soil at the Nevada TestSite. The project has been systematically approached. A thorough review and summary was completed for: (1) The NTS soil geological, geochemical and physical characteristics; (2) The characteristics and chemical form of the plutonium that is in these soils; (3) Previous volume reduction technologies that have been attempted on the NTS soils; (4) Vendors with technology that may be applicable; and (5) Related needs at other DOE sites. Soils from the Nevada TestSite were collected and delivered to the CETL. Soils were characterized for Pu-239/240, Am-241 and gross alpha. In addition, wet sieving and the subsequent characterization were performed on soils before and after attrition scrubbing to determine the particle size distribution and the distribution of Pu-239/240 and gross alpha as a function of particle size. Sequential extraction was performed on untreated soil to provide information about how tightly bound the plutonium was to the soil. Magnetic separation was performed to determine if this could be useful as part of a treatment approach. Using the information obtained from these reviews, three vendors were selected to demonstration their volume reduction technologies at the CETL. Two of the three technologies, bioremediation and soil washing, met the performance criteria. Both were able to significantly reduce the concentration plutonium in the soil from around 1100 pCi/g to 200 pCi/g or less with a volume reduction of around 95%, well over the target 70%. These results are especially encouraging because they indicate significant improvement over that obtained in these earlier pilot and field studies. Additional studies are recommended.

This Corrective Action Plan (CAP) has been prepared for Corrective Action Unit (CAU) 563, Septic Systems, in accordance with the Federal Facility Agreement and Consent Order. CAU 563 consists of four Corrective Action Sites (CASs) located in Areas 3 and 12 of the Nevada TestSite. CAU 563 consists of the following CASs: #2; CAS 03-04-02, Area 3 Subdock Septic Tank #2; CAS 03-59-05, Area 3 Subdock Cesspool #2; CAS 12-59-01, Drilling/Welding Shop Septic Tanks #2; CAS 12-60-01, Drilling/Welding Shop Outfalls Site characterization activities were performed in 2007, and the results are presented in Appendix A of the CAU 563 Corrective Action Decision Document. The scope of work required to implement the recommended closure alternatives is summarized below. #2; CAS 03-04-02, Area 3 Subdock Septic Tank, contains no contaminants of concern (COCs) above action levels. No further action is required for this site; however, as a best management practice (BMP), all aboveground features (e.g., riser pipes and bumper posts) will be removed, the septic tank will be removed, and all open pipe ends will be sealed with grout. #2; CAS 03-59-05, Area 3 Subdock Cesspool, contains no COCs above action levels. No further action is required for this site; however, as a BMP, all aboveground features (e.g., riser pipes and bumper posts) will be removed, the cesspool will be abandoned by filling it with sand or native soil, and all open pipe ends will be sealed with grout. #2; CAS 12-59-01, Drilling/Welding Shop Septic Tanks, will be clean closed by excavating approximately 4 cubic yards (yd3) of arsenic- and chromium-impacted soil. In addition, as a BMP, the liquid in the South Tank will be removed, the North Tank will be removed or filled with grout and left in place, the South Tank will be filled with grout and left in place, all open pipe ends will be sealed with grout or similar material, approximately 10 yd3 of chlordane-impacted soil will be excavated, and debris within the CAS boundary will be removed. #2; CAS 12-60-01, Drilling/Welding Shop Outfalls, contains no COCs above action levels. No further action is required for this site; however, as a BMP, three drain pipe openings will be sealed with grout.

This Corrective Action Decision Document/Closure Report has been prepared for Corrective Action Unit (CAU) 557, Spills and Tank Sites, in Areas 1, 3, 6, and 25 of the Nevada TestSite, Nevada, in accordance with the Federal Facility Agreement and Consent Order. Corrective Action Unit 557 comprises the following corrective action sites (CASs): • 01-25-02, Fuel Spill • 03-02-02, Area 3 Subdock UST • 06-99-10, Tar Spills • 25-25-18, Train Maintenance Bldg 3901 Spill Site The purpose of this Corrective Action Decision Document/Closure Report is to identify and provide the justification and documentation that supports the recommendation for closure of the CAU 557 CASs with no further corrective action. To achieve this, a corrective action investigation (CAI) was conducted from May 5 through November 24, 2008. The CAI activities were performed as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 557: Spills and Tank Sites, Nevada TestSite, Nevada.

Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada TestSite unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada TestSite, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots'' from the concrete vault, and the drilling removal of the cement-lined vault sump. Field activities began on November 28, 2000, and ended on December 4, 2000. After verification samples were collected, the vault was repaired with cement. The concrete vault sump, soil excavated beneath the sump, and compactable hot line trash were disposed at the Area 23 Sanitary Landfill. The vault interior was field surveyed following the removal of waste to verify that unrestricted release criteria had been achieved. Since the site is closed by unrestricted release decontamination and verification, post-closure care is not required.

The Nevada TestSite (NTS) is operated by the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office. From 1951 through 1992, the NTS was operated as the nation's site for nuclear weapons testing. The release of man-made radionuclides from the NTS as a result of testing activities has been monitored since the first decade of atmospheric testing. After 1962, when nuclear tests were conducted only underground, the radiation exposure to the public surrounding the NTS was greatly reduced. After the 1992 moratorium on nuclear testing, radiation monitoring on the NTS focused on detecting airborne radionuclides which come from historically contaminated soils resuspended into the air (e.g., by winds) and tritium-contaminated soil moisture emitted to the air from soils through evapotranspiration. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations [CFR] Part 61 Subpart H) limits the release of radioactivity from a U.S. Department of Energy facility (e.g., the NTS) to 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This is the dose limit established for someone living off of the NTS from radionuclides emitted to air from the NTS. This limit does not include the radiation doses that members of the public may receive through the intake of radioactive particles unrelated to NTS activities, such as those that come from naturally occurring elements in the environment (e.g., naturally occurring radionuclides in soil or radon gas from the earth or natural building materials), or from other man-made sources (e.g., medical treatments). The NTS demonstrates compliance using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the U.S. Environmental Protection Agency for use on the NTS in 2001 and has been the sole method used since 2005. There are six critical receptor locations on the NTS that are actually pseudocritical receptor locations because they are hypothetical receptor locations; no person actually resides at these onsite locations. Annual average concentrations of detected radionuclides are compared with Concentration Levels (CL) for Environmental Compliance values listed in 40 CFR 61, Appendix E, Table 2. Compliance is demonstrated if the sum of fractions (CL/measured concentrations) of all detected radionuclides at each pseudo-critical receptor location is less than one. In 2007, as in all previous years for which this report has been produced, the NTS has demonstrated that the potential dose to the public from radiological emissions to air from current and past NTS activities is well below the 10 mrem/yr dose limit. Air sampling data collected onsite at each of the six pseudo-critical receptor stations on the NTS had average concentrations of nuclear test-related radioactivity that were a fraction of the limits listed in Table 2 in Appendix E of 40 CFR 61. They ranged from less than 1 percent to a maximum of 20 percent of the allowed NESHAP limit. Because the nearest member of the public resides approximately 20 kilometers (12 miles) from the NTS boundary, concentrations at this location would be only a small fraction of that measured on the NTS.

Nuclear testing at and around the Nevada TestSite (NTS) resulted in plutonium (Pu) contamination of the soil over an area of several thousands of acres. The objective of this project was to evaluate the potential of five different processes to reduce the volume of Pu-contaminated soil from three different areas, namely Areas 11, 13, and 52. Volume reduction was to be accomplished by concentrating the Pu into a small but highly contaminated soil fraction, thereby greatly reducing the volume of soil requiring disposal. The processes tested were proposed by Paramag Corp. (PARAMAG), Advanced Processing Technologies Inc. (APT), Lockheed Environmental Systems and Technologies (LESAT), Nuclear Remediation Technologies (NRT), and Scientific Ecology Group (SEG). Because of time and budgetary restraints, the NRT and SEG processes were tested with soil from Area 11 only. These processes typically included a preliminary soil conditioning step (e.g., attrition scrubbing, wet sieving), followed by a more advanced process designed to separate Pu from the soil, based on physiochemical properties of Pu compounds (e.g., magnetic susceptibility, specific gravity). Analysis of the soil indicates that a substantial fraction of the total Pu contamination is typically confined in a relatively narrow and small particle size range. Processes which were able to separate this highly contaminated soil fraction (using physical methods, e.g., attrition scrubbing, wet sieving), from the rest of the soil achieved volume (mass) reductions on the order of 70%. The advanced, more complex processes tested did not enhance volume reduction. The primary reason why processes that rely on the dependence of settling velocity on density differences failed was the very fine grain size of the Pu-rich particles.

Corrective Action Unit (CAU) 105 is located in Area 2 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 105 is a geographical grouping of sites where there has been a suspected release of contamination associated with atmospheric nuclear testing. This document describes the planned investigation of CAU 105, which comprises the following corrective action sites (CASs): • 02-23-04, Atmospheric TestSite - Whitney • 02-23-05, Atmospheric TestSite T-2A • 02-23-06, Atmospheric TestSite T-2B • 02-23-08, Atmospheric TestSite T-2 • 02-23-09, Atmospheric TestSite - Turk These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 30, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 105. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with all CAU 105 CASs are from atmospheric nuclear testing activities. The presence and nature of contamination at CAU 105 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose at sample locations to the dose-based final action level. The total effective dose will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; DOE, Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted after the plan is approved.

This Closure Report presents information supporting the closure of Corrective Action Unit (CAU) 177: Mud Pits and Cellars, Nevada TestSite, Nevada. This Closure Report complies with the requirements of the Federal Facility Agreement and Consent Order (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. The Corrective Action Sites (CASs) within CAU 177 are located within Areas 8, 9, 19, and 20 of the Nevada TestSite. The purpose of this Closure Report is to provide documentation supporting the completed corrective actions and data that confirm the corrective actions implemented for CAU 177 CASs.

This Corrective Action Decision Document/Closure Report (CADD/CR) was prepared by the Defense Threat Reduction Agency (DTRA) for Corrective Action Unit (CAU) 383, Area 12 E-Tunnel Sites, which is the joint responsibility of DTRA and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This CADD/CR is consistent with the requirements of the Federal Facility Agreement and Consent Order (FFACO) agreed to by the State of Nevada, the DOE, and the U.S. Department of Defense. Corrective Action Unit 383 is comprised of three Corrective Action Sites (CASs) and two adjacent areas: • CAS 12-06-06, Muckpile • CAS 12-25-02, Oil Spill • CAS 12-28-02, Radioactive Material • Drainage below the Muckpile • Ponds 1, 2, and 3 The purpose of this CADD/CR is to provide justification and documentation to support the recommendation for closure with no further corrective action, by placing use restrictions at the three CASs and two adjacent areas of CAU 383.

Settlement Agreement for Transuranic (TRU) Mixed Settlement Agreement for Transuranic (TRU) Mixed Waste Storage Issues at the Nevada TestSite (NTS) State Nevada Agreement Type Settlement Agreement Legal Driver(s) RCRA Scope Summary Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS Parties DOE; Nevada Department of Environmental Protection Date 6/11/1992 SCOPE * Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS. ESTABLISHING MILESTONES * Within 90 days of the effective date of this Agreement, DOE will provide to NDEP documentation of why the current inventory of TRU mixed waste cannot be removed

Observational data on Nevada TestSite (NTS) faults were gathered from a variety of sources, including surface and tunnel exposures, core samples, geophysical logs, and down-hole cameras. These data show that NTS fault characteristics and fault zone permeability structures are similar to those of faults studied in other regions. Faults at the NTS form complex and heterogeneous fault zones with flow properties that vary in both space and time. Flow property variability within fault zones can be broken down into four major components that allow for the development of a simplified, first approximation model of NTS fault zones. This conceptual model can be used as a general guide during development and evaluation of groundwater flow and contaminate transport models at the NTS.

The sorption behavior of americium (Am), plutonium (Pu), neptunium (Np), and uranium (U) in perched Rainier Mesa tunnel water was investigated. Both volcanic zeolitized tuff samples and groundwater samples were collected from Rainier Mesa, Nevada TestSite, NV for a series of batch sorption experiments. Sorption in groundwater with and without the presence of dissolved organic matter (DOM) was investigated. Am(III) and Pu(IV) are more soluble in groundwater that has high concentrations of DOM. The sorption K{sub d} for Am(III) and Pu(IV) on volcanic zeolitized tuff was up to two orders of magnitude lower in samples with high DOM (15 to 19 mg C/L) compared to samples with DOM removed (Rainier Mesa, the low actinide Kd values measured in groundwater with high DOM concentrations must be incorporated in predictive transport models.

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DOEIJEA-1219 DOEIJEA-1219 ENVIRONMENTAL ASSESSMENT HOE CREEK UNDERGROUND COAL GASIFICATION TESTSITE REMEDIATION CAMPBELL COUNTY, WYOMING October 1997 U.S. DEPARTMENT OF ENERGY FEDERAL ENERGY TECHNOLOGY CENTER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or use- fulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any spe- cific commercial product, process. or service by trade name, trademark, manufac-

The Nevada TestSite Underground Safety and Health Standards Working Group was formed at the direction of John D. Stewart, Director, Nevada TestSite Office in April, 1990. The objective of the Working Group was to compile a safety and health standard from the California Tunnel Safety Orders and OSHA for the underground operations at the NTS, (excluding Yucca Mountain). These standards are called the NTS U/G Safety and Health Standards. The Working Group submits these standards as a RECOMMENDATION to the Director, NTSO. Although the Working Group considers these standards to be the most integrated and comprehensive standards that could be developed for NTS Underground Operations, the intent is not to supersede or replace any relevant DOE orders. Rather the intent is to collate the multiple safety and health references contained in DOE Order 5480.4 that have applicability to NTS Underground Operations into a single safety and heath standard to be used in the underground operations at the NTS. Each portion of the standard was included only after careful consideration by the Working Group and is judged to be both effective and appropriate. The specific methods and rationale used by the Working Group are outlined as follows: The letter from DOE/HQ, dated September 28, 1990 cited OSHA and the CTSO as the safety and health codes applicable to underground operations at the NTS. These mandated codes were each originally developed to be comprehensive, i.e., all underground operations of a particular type (e.g., tunnels in the case of the CTSO) were intended to be adequately regulated by the appropriate code. However, this is not true; the Working Group found extensive and confusing overlap in the codes in numerous areas. Other subjects and activities were addressed by the various codes in cursory fashion or not at all.

This report contains an initial definition of the field tests proposed for the Yucca Mountain Project repository sealing program. The tests are intended to resolve various performance and emplacement concerns. Examples of concerns to be addressed include achieving selected hydrologic and structural requirements for seals, removing portions of the shaft liner, excavating keyways, emplacing cementitious and earthen seals, reducing the impact of fines on the hydraulic conductivity of fractures, efficient grouting of fracture zones, sealing of exploratory boreholes, and controlling the flow of water by using engineered designs. Ten discrete tests are proposed to address these and other concerns. These tests are divided into two groups: Seal component tests and performance confirmation tests. The seal component tests are thorough small-scale in situ tests, the intermediate-scale borehole seal tests, the fracture grouting tests, the surface backfill tests, and the grouted rock mass tests. The seal system tests are the seepage control tests, the backfill tests, the bulkhead test in the Calico Hills unit, the large-scale shaft seal and shaft fill tests, and the remote borehole sealing tests. The tests are proposed to be performed in six discrete areas, including welded and non-welded environments, primarily located outside the potential repository area. The final selection of sealing tests will depend on the nature of the geologic and hydrologic conditions encountered during the development of the Exploratory Studies Facility and detailed numerical analyses. Tests are likely to be performed both before and after License Application.

This Corrective Action Decision Document/Closure Report presents information supporting the closure of Corrective Action Unit (CAU) 570: Area 9 Yucca Flat Atmospheric TestSites, Nevada National Security Site, Nevada. This complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The purpose of the CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed.

Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval.

This Streamlined Approach for Environmental Restoration Plan provides the details for the closure of Corrective Action Unit (CAU) 489: WWII UXO Sites, Tonopah Test Range. CAU 489 is located at the Tonopah Test Range and is currently listed in Appendix III of the Federal Facility Agreement and Consent Order of 1996.

Bechtel Nevada; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

The role fractures play in the movement of groundwater through zeolitic tuffs that form the tuff confining unit (TCU) beneath Yucca Flat, Nevada TestSite, is poorly known. This is an important uncertainty, because beneath most of Yucca Flat the TCU lies between the sources of radionuclide contaminants produced by historic underground nuclear testing and the regional carbonate aquifer. To gain a better understanding of the role fractures play in the movement of groundwater and radionuclides through the TCU beneath Yucca Flat, a fracture analysis focusing on hydraulic properties was performed on conventional cores from four vertical exploratory holes in Area 7 of Yucca Flat that fully penetrate the TCU. The results of this study indicate that the TCU is poorly fractured. Fracture density for all fractures is 0.27 fractures per vertical meter of core. For open fractures, or those observed to have some aperture, the density is only 0.06 fractures per vertical meter of core. Open fractures are characterized by apertures ranging from 0.1 to 10 millimeter, and averaging 1.1 millimeter. Aperture typically occurs as small isolated openings along the fracture, accounting for only 10 percent of the fracture volume, the rest being completely healed by secondary minerals. Zeolite is the most common secondary mineral occurring in 48 percent of the fractures observed.

This report presents a chronological summary of previous technology development efforts concerning the rotary microfiltration (RMF) unit from SpinTek{trademark}. Rotary microfiltration has been developed for high radiation application over the last decades as one of the optional filtration techniques for supplemental treatment. Supplemental treatment includes a near- or in-tank solids separation and subsequent cesium removal unit, followed by an immobilization technique; this includes options such as steam reforming, bulk vitrification or cast stone (grout). The main difference between RMF and standard cross flow filtration (CFF) is the disconnection of filtrate flux from feed velocity; i.e., filtrate flux is only dependent on transmembrane pressure, filter fouling and temperature. These efforts have been supported by the U.S. Department of Energy (DOE), Office of Cleanup Technologies since the 1990s by their Environmental Management Program (currently EM-31). In order to appropriately address future testing needs, a compilation of the relevant previous testing reports was essential. This compendium does not intend to cover all of the presentations/reports that were produced over the last decades but focuses on those of relevance for developing an RMF unit fit for deployment at the Hanford site. The report is split into three parts: (1) an introductory overview, (2) Figure 1 graphically covering the main development steps and its key players and (3) a more detailed table of the citations and brief descriptions of results and recommendations.

The US Department of Energy, Nevada Field Office, has proposed a nuclear test at drill hole U19aq (902100N/585000E, Nevada Coordinate System, Central Zone) on Pahute Mesa, Nevada TestSite, Nevada. In compliance with Section 106 of the National Historic Preservation Act, the DOE/NV had the Quatenary Sciences Center, Desert Research Institute, identify and evaluate the potential effects of this activity on cultural resources. To determine the nature of cultural resources in the area, DRI conducted a Class III intensive archaeological survey of an approximately 1-km{sup 2} area around the drill hole. That survey, conducted in June 1985, located and recorded 20 archaeological sites. Two of those sites, interpreted as temporary camps of ancient hunters and gatherers, covered an extensive portion of the area proposed for nuclear testing. Half the sites were small concentrations of artifacts or isolated artifacts and were collected at the time of their discovery and 10 sites were left in place. Those sites were in danger of being adversely affected by the land-disturbing activities proposed at the drill hole. In August and September 1985, DRI conducted limited test excavations (15 test units) at those sites to further evaluate their scientific significance and to provide information that could be used in designing a plan for data recovery.

The US Department of Energy, Nevada Field Office, has proposed a nuclear test at drill hole U19aq (902100N/585000E, Nevada Coordinate System, Central Zone) on Pahute Mesa, Nevada TestSite, Nevada. In compliance with Section 106 of the National Historic Preservation Act, the DOE/NV had the Quatenary Sciences Center, Desert Research Institute, identify and evaluate the potential effects of this activity on cultural resources. To determine the nature of cultural resources in the area, DRI conducted a Class III intensive archaeological survey of an approximately 1-km[sup 2] area around the drill hole. That survey, conducted in June 1985, located and recorded 20 archaeological sites. Two of those sites, interpreted as temporary camps of ancient hunters and gatherers, covered an extensive portion of the area proposed for nuclear testing. Half the sites were small concentrations of artifacts or isolated artifacts and were collected at the time of their discovery and 10 sites were left in place. Those sites were in danger of being adversely affected by the land-disturbing activities proposed at the drill hole. In August and September 1985, DRI conducted limited test excavations (15 test units) at those sites to further evaluate their scientific significance and to provide information that could be used in designing a plan for data recovery.

The Federal Facility Agreement and Consent Order was entered into by the State of Nevada; U.S. Department of Energy, and the U.S. Department of Defense to identify sites of potential historical contamination and implement corrective actions based on public health and environmental considerations. The facilities subject to this agreement include the Nevada TestSite (NTS), parts of the Tonopah Test Range, parts of the Nellis Air Force Range, the Central Nevada Test Area, and the Project Shoal Area. Corrective Action Sites (CASs) are areas potentially requiring corrective actions and may include solid waste management units, individual disposal, or release sites. Based on geography, technical similarity, agency responsibility, or other appropriate reasons, CASs are grouped together into corrective Action Units (CAUs) for the purposes of determining corrective actions. This report contains the Closure Verification Forms for cleanup activities that were performed at six CASs within CAU 212 on the NTS. The form for each CAS provides the location, directions to the site, general description, and photographs of the site before and after cleanup activities. Housekeeping activities at these sites included removal of debris, drums, batteries, scrap metal, and other material. Based on these activities, no further action is required at these CASs.

This Corrective Action Investigation Plan (CAIP) contains project-specific information for conducting site investigation activities at Corrective Action Unit (CAU) 554: Area 23 Release Site, Nevada TestSite, Nevada. Information presented in this CAIP includes facility descriptions, environmental sample collection objectives, and criteria for the selection and evaluation of environmental samples. Corrective Action Unit 554 is located in Area 23 of the Nevada TestSite, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 554 is comprised of one Corrective Action Site (CAS), which is: 23-02-08, USTs 23-115-1, 2, 3/Spill 530-90-002. This site consists of soil contamination resulting from a fuel release from underground storage tanks (USTs). Corrective Action Site 23-02-08 is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation prior to evaluating corrective action alternatives and selecting the appropriate corrective action for this CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document for CAU 554. Corrective Action Site 23-02-08 will be investigated based on the data quality objectives (DQOs) developed on July 15, 2004, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; and contractor personnel. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 554. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to CAS 23-02-08. The scope of the corrective action investigation for CAU 554 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Perform field screening. (3) Collect and submit environmental samples for laboratory analysis to determine if contaminants of concern are present. (4) If contaminants of concern are present, collect additional step-out samples to define the extent of the contamination. (5) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this CAIP will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval of the plan.

This document constitutes an addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 452: Historical Underground Storage Tank Release Sites, Nevada TestSite, Nevada, April 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada TestSite, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the URs for CASs: • 25-25-09, Spill H940825C (from UST 25-3101-1) • 25-25-14, Spill H940314E (from UST 25-3102-3) • 25-25-15, Spill H941020E (from UST 25-3152-1) These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

This document constitutes an addendum to the Closure Report for Corrective Action Unit 326: Areas 6 and 27 Release Sites, Nevada TestSite, Nevada (Revision 1), December 2002 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada TestSite, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the UR for CAS 06-25-01, CP-1 Heating Oil Release. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was reevaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.

This document constitutes an addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 454: Historical Underground Storage Tank Release Sites, Nevada TestSite, Nevada, April 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada TestSite, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the URs for CASs: • 12-25-08, Spill H950524F (from UST 12-B-1) • 12-25-10, Spill H950919A (from UST 12-COMM-1) These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

The US Department of Energy (DOE) is responsible for disposing of a variety of radioactive and mixed wastes, some of which are considered special-case waste because they do not currently have a clear disposal option. The DOE`s Nevada Field Office contracted with Sandia National Laboratories to investigate the possibility of disposing of some of this special-case waste at the Nevada TestSite (NTS). As part of this investigation, a review of a near-surface and subsurface disposal options that was performed to develop alternative disposal configurations for special-case waste disposal at the NTS. The criteria for the review included (1) configurations appropriate for disposal at the NTS; (2) configurations for disposal of waste at least 100 ft below the ground surface; (3) configurations for which equipment and technology currently exist; and (4) configurations that meet the special requirements imposed by the nature of special-case waste. Four options for subsurface disposal of special-case waste are proposed: mined consolidated rock, mined alluvium, deep pits or trenches, and deep boreholes. Six different methods for near-surface disposal are also presented: earth-covered tumuli, above-grade concrete structures, trenches, below-grade concrete structures, shallow boreholes, and hydrofracture. Greater confinement disposal (GCD) in boreholes at least 100 ft deep, similar to that currently practiced at the GCD facility at the Area 5 Radioactive Waste Management Site at the NTS, was retained as the option that met the criteria for the review. Four borehole disposal configurations are proposed with engineered barriers that range from the native alluvium to a combination of gravel and concrete. The configurations identified will be used for system analysis that will be performed to determine the disposal configurations and wastes that may be suitable candidates for disposal of special-case wastes at the NTS.

Corrective Action Unit (CAU) 224 is located in Areas 02, 03, 05, 06, 11, and 23 of the Nevada TestSite, which is situated approximately 65 miles northwest of Las Vegas, Nevada. CAU 224 is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 as Decon Pad and Septic Systems and is comprised of the following nine Corrective Action Sites (CASs): CAS 02-04-01, Septic Tank (Buried); CAS 03-05-01, Leachfield; CAS 05-04-01, Septic Tanks (4)/Discharge Area; CAS 06-03-01, Sewage Lagoons (3); CAS 06-05-01, Leachfield; CAS 06-17-04, Decon Pad and Wastewater Catch; CAS 06-23-01, Decon Pad Discharge Piping; CAS 11-04-01, Sewage Lagoon; and CAS 23-05-02, Leachfield. The Nevada Division of Environmental Protection (NDEP)-approved corrective action alternative for CASs 02-04-01, 03-05-01, 06-03-01, 11-04-01, and 23-05-02 is no further action. As a best management practice, the septic tanks and distribution box were removed from CASs 02-04-01 and 11-04-01 and disposed of as hydrocarbon waste. The NDEP-approved correction action alternative for CASs 05-04-01, 06-05-01, 06-17-04, and 06-23-01 is clean closure. Closure activities for these CASs included removing and disposing of radiologically and pesticide-impacted soil and debris. CAU 224 was closed in accordance with the NDEP-approved CAU 224 Corrective Action Plan (CAP). The closure activities specified in the CAP were based on the recommendations presented in the CAU 224 Corrective Action Decision Document (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2005). This Closure Report documents CAU 224 closure activities. During closure activities, approximately 60 cubic yards (yd3) of mixed waste in the form of soil and debris; approximately 70 yd{sup 3} of sanitary waste in the form of soil, liquid from septic tanks, and concrete debris; approximately 10 yd{sup 3} of hazardous waste in the form of pesticide-impacted soil; approximately 0.5 yd{sup 3} of universal waste in the form of fluorescent light bulbs; and approximately 0.5 yd{sup 3} of low-level waste in the form of a radiologically impacted fire hose rack were generated, managed, and disposed of appropriately. Waste minimization techniques, such as the utilization of laboratory analysis and field screening to guide the extent of excavations, were employed during the performance of closure work.

Sample records for test site nye from the National Library of Energy Beta (NLEBeta)

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This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives (CAAs) appropriate for the closure of Corrective Action Unit (CAU) 536: Area 3 Release Site, Nevada TestSite, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 536 consists of a single Corrective Action Site (CAS): 03-44-02, Steam Jenny Discharge. The CAU 536 site is being investigated because existing information on the nature and extent of possible contamination is insufficient to evaluate and recommend corrective action alternatives for CAS 03-44-02. The additional information will be obtained by conducting a corrective action investigation (CAI) prior to evaluating CAAs and selecting the appropriate corrective action for this CAS. The results of this field investigation are to be used to support a defensible evaluation of corrective action alternatives in the corrective action decision document. Record of Technical Change No. 1 is dated 3-2004.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

In February 1997, the U.S. Department of Energy, Nevada Operations Office issued the Mitigation Action Plan which addressed potential impacts described in the “Final Environmental Impact Statement for the Nevada TestSite and Off-Site Locations in the State of Nevada” (DOE/EIS 0243). The U.S. Department of Energy, Nevada Operations Office committed to several actions, including the preparation of an annual report, which summarizes waste shipments to and from the Nevada TestSite (NTS) Radioactive Waste Management Sites (RWMS) at Area 3 and Area 5. This document satisfies requirements with regard to low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) transported to or from the NTS during fiscal year (FY) 2006.

Corrective Action Unit (CAU) 254 is located in Area 25 of the Nevada TestSite (NTS), approximately 100 kilometers (km) (62 miles) northwest of Las Vegas, Nevada. The site is located within the Reactor Maintenance, Assembly and Disassembly (R-MAD) compound and consists of Building 3126, two outdoor decontamination pads, and surrounding areas within an existing fenced area measuring approximately 50 x 37 meters (160 x 120 feet). The site was used from the early 1960s to the early 1970s as part of the Nuclear Rocket Development Station program to decontaminate test-car hardware and tooling. The site was reactivated in the early 1980s to decontaminate a radiologically contaminated military tank. This Closure Report (CR) describes the closure activities performed to allow un-restricted release of the R-MAD Decontamination Facility.

The Nevada TestSite-Directed Research and Development (SDRD) program completed a very successful year of research and development activities in FY 2007. Twenty-nine new projects were selected for funding this year, and eight projects started in FY 2006 were brought to conclusion. The total funds expended by the SDRD program were $5.67 million, for an average per-project cost of $153 thousand. An external audit conducted in September 2007 verified that appropriate accounting practices were applied to the SDRD program. Highlights for the year included: programmatic adoption of 8 SDRD-developed technologies; the filing of 9 invention disclosures for innovation evolving from SDRD projects; participation in the tri-Lab Laboratory Directed Research and Development (LDRD) and SDRD Symposium that was broadly attended by Nevada TestSite (NTS), National Nuclear Security Administration (NNSA), LDRD, U.S. Department of Homeland Security (DHS), and U.S. Department of Defense (DoD) representatives; peer reviews of all FY 2007 projects; and the successful completion of 37 R&D projects, as presented in this report. In response to a company-wide call, authors throughout the NTS complex submitted 182 proposals for FY 2007 SDRD projects. The SDRD program has seen a dramatic increase in the yearly total of submitted proposals--from 69 in FY 2002 to 182 this year--while the number of projects funded has actually decreased from a program high of 57 in FY 2004. The overall effect of this trend has helped ensure an increasingly competitive program that benefited from a broader set of innovative ideas, making project selection both challenging and rewarding. Proposals were evaluated for technical merit, including such factors as innovation, probability of success, potential benefit, and mission applicability. Authors and reviewers benefited from the use of a shortfalls list entitled the 'NTS Technology Needs Assessment' that was compiled from NTS, National Weapons Laboratory (NWL), and NNSA sources. This tool continues to be of considerable value in aligning the SDRD program with mission priorities, and was expanded in FY 2007 to include technology development needs from the DHS and other agencies with missions closely aligned to that of the NTS.

The Nevada TestSite (NTS) is operated by the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office. From 1951 through 1992, the NTS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NTS activities has been monitored since the initiation of atmospheric testing. Limitation to under-ground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NTS. After nuclear testing ended in 1992, NTS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by winds) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of tritium were also emitted to air at the North Las Vegas Facility (NLVF), an NTS support complex in the city of North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations [CFR] Part 61 Subpart H) (CFR, 2008a) limits the release of radioactivity from a U.S. Department of Energy facility (e.g., the NTS) to 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation not related to NTS activities. Unrelated doses could come from naturally occurring radioactive elements or from other man-made sources such as medical treatments. The NTS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the U.S. Environmental Protection Agency for use on the NTS in 2001 and has been the sole method used since 2005. Six locations on the NTS have been established to act as critical receptor locations to demonstrate compliance with the NESHAP limit. These locations are actually pseudo-critical receptor stations, because no member of the public actually resides at these onsite locations. Compliance is demonstrated if the measured annual average concentration of each detected radionuclide at each of these locations is less than the NESHAP Concentration Levels (CLs) for Environmental Compliance listed in 40 CFR 61, Appendix E, Table 2 (CFR, 2008a). At any one location, if multiple radionuclides are detected then compliance with NESHAP is demonstrated when the sum of the fractions (determined by dividing each radionuclide's concentration by its CL and then adding the fractions together) is less than 1.0. In 2008, the potential dose from radiological emissions to air, from both current and past NTS activities, at onsite compliance monitoring stations was a maximum of 1.9 mrem/yr; well below the 10 mrem/yr dose limit. Air sampling data collected at all six pseudo-critical receptor stations had average concentrations of radioactivity that were a fraction of the CL values listed in Table 2 in Appendix E of 40 CFR 61 (CFR, 2008a). Concentrations ranged from less than 1 percent to a maximum of 19 percent of the allowed NESHAP limit. Because the nearest member of the public resides approximately 20 kilometers (12 miles) from the NTS boundary, concentrations at this location would be only a small fraction of that measured on the NTS. Potential dose to the public from NLVF was also very low at 0.00006 mrem/yr; more than 160,000 times lower than the 10 mrem/yr limit.

The interpretation of chemical analyses of groundwater collected at and near the Nevada TestSite (NTS) has been vital in developing conceptual models of groundwater flow in the area. These conceptual models are tested using recent chemical data generated by the Desert Research Institute, as well as historic analyses from the US Geological Survey. A total of 81 wells are represented by analyses from 1957 to 1990, with generally excellent agreement between repeat samples from the same location. As identified by previous workers, three hydrochemical facies are represented by the samples: Ca-Mg-HCO{sub 3} water in carbonate rocks or alluvium derived from carbonates, Na-K-HCO{sub 3} water in volcanic rocks and alluvium derived from volcanic rocks, and a mixed fades found in many carbonate and alluvium water samples, and some volcanic waters. There is a general lack of lateral continuity in chemical characteristics along presumed flowpaths within each hydrologic unit (alluvium, carbonate, and volcanic). Though a lack of continuity between basins on the east side of the NTS was expected for water in alluvial and volcanic units due to the absence of interbasin flow, chemical differences observed within individual basins suggest a dominance of vertical over lateral flow. Groundwater in volcanic materials on the east side of Yucca and Frenchman Flats and on the west side of Pahute Mesa and Yucca Mountain has a nearly pure Na-K-HCO{sub 3} signature that reflects contact with primarily volcanic material. Groundwater in volcanic units in the middle of the NTS and on the east side of Pahute Mesa contains a higher proportion of Ca, Mg, Cl, and SO{sub 4} than the other volcanic waters and indicates the contribution of water from the upper carbonate aquifer and/or hydrothermally altered regions.

Groundwater monitoring at the Nevada TestSite (NTS) is conducted to detect the presence of radionuclides produced by underground nuclear testing and to verify the quality and safety of groundwater supplies as required by the State of Nevada and federal regulations, and by U.S. Department of Energy (DOE) Orders. Groundwater is monitored at water-supply wells and at other boreholes and wells not specifically designed or located for traditional groundwater monitoring objectives. Different groundwater monitoring programs at the NTS are conducted by several DOE Nevada Operations Office (DOE/NV) contractors. Presently, these individual groundwater monitoring programs have not been assessed or administered under a comprehensive planning approach. Redundancy exists among the programs in both the sampling locations and the constituents analyzed. Also, sampling for certain radionuclides is conducted more frequently than required. The purpose of this report is to review the existing NTS groundwater monitoring programs and make recommendations for modifying the programs so a coordinated, streamlined, and comprehensive monitoring effort may be achieved by DOE/NV. This review will be accomplished in several steps. These include: summarizing the present knowledge of the hydrogeology of the NTS and the potential radionuclide source areas for groundwater contamination; reviewing the existing groundwater monitoring programs at the NTS; examining the rationale for monitoring and the constituents analyzed; reviewing the analytical methods used to quantify tritium activity; discussing monitoring network design criteria; and synthesizing the information presented and making recommendations based on the synthesis. This scope of work was requested by the DOE/NV Hydrologic Resources Management Program (HRMP) and satisfies the 1993 (fiscal year) HRMP Groundwater Monitoring Program Review task.

Corrective Action Unit (CAU) 106 is located in Area 5 of the Nevada TestSite, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 106 comprises the five corrective action sites (CASs) listed below: •05-23-02, GMX Alpha Contaminated Area •05-23-05, Atmospheric TestSite - Able •05-45-01, Atmospheric TestSite - Hamilton •05-45-04, 306 GZ Rad Contaminated Area •05-45-05, 307 GZ Rad Contaminated Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 19, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 106. The presence and nature of contamination at CAU 106 will be evaluated based on information collected from a field investigation. The CAU includes land areas impacted by the release of radionuclides from a weapons-effect tower test (CAS 05-45-01), a weapons-related airdrop test (CAS 05-23-05), “equation of state” experiments (CAS 05-23-02), and unknown support activities at two sites (CAS 05-45-04 and CAS 05-45-05). Surface-deposited radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample plot locations to the dose-based final action level. The TED will be calculated as the total of separate estimates of internal and external doses. Results from the analysis of soil samples collected from sample plots will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample plot will be used to measure external radiological dose. The presence and nature of contamination from other types of releases (such as migration and excavation as well as any potential releases discovered during the investigation) will be evaluated using soil samples collected from the locations most likely containing contamination, if present. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 106 includes the following activities: •Conduct radiological surveys. •Collect and submit environmental samples for laboratory analysis to determine internal dose rates and the presence of contaminants of concern. •If contaminants of concern are present, collect additional samples to define the extent of the contamination and determine the area where TED at the site exceeds final action levels (i.e., corrective action boundary). •Collect samples of investigation-derived waste, as needed, for waste management purposes.

Micrometeorological and soil-moisture data were collected at two instrumented sites on Rainier Mesa at the Nevada TestSite, January 1, 2002/August 23, 2005. Data collected at each site include net radiation, air temperature, and relative humidity at two heights; wind speed and direction; subsurface soil heat flux; subsurface soil temperature; volumetric soil water; and matric water potential. These data were used to estimate 20-minute average and daily average evapotranspiration values. The data presented in this report are collected and calculated evapotranspiration rates.

Gravity and ground magnetic data collected along six traverses across Fortymile Wash, in the southwest quadrant of the Nevada TestSite suggest that there are no significant vertical offsets below Fortymile Wash. The largest gravity and magnetic anomaly, in the vicinity of Fortymile Wash, is produced by the Paintbrush fault, on the west flank of Fran Ridge. Inferred vertical offset is about 250 {+-} 60 m (800 {+-} 200 ft). Geophysical data indicate that the fault is about 300 m (1,000 ft) east of its mapped, but concealed location. North of Busted Butte, near Fran Ridge, geophysical data do not preclude the existence of small vertical offsets bounding Fortymile Wash. However, gravity and magnetic profiles south of Busted Butte show little correlation to those to the north and suggest that vertical offsets, comparable in size to the Paintbrush fault, are not present. Density profiling, a technique used to determine the average density of small topographic features, suggests that the density of near-surface material in the vicinity of Fortymile Wash is 1.80 to 2.00 g/cm{sup 3}.

Quartz sand derived from alluvial fans that drain different lithologies at the Nevada TestSite can be distinguished on the basis of grain shape as described by the Fourier series in closed form. Specifically, we examined tuff units from the Piapi Canyon and Indian Trail Formations as well as carbonate-bearing clastic units from the Eleana Formation. Discrimiation between rock types was accomplished by examining the mean harmonic amplitude spectra and the grain shape frequency distributions at those harmonics that exhibit significant chi-square values. The results of these analyses indicate that the tuffs can be easily distinguished from the clastics. However, differences between samples from genetically similar rock types are not as prominent. Grain shape frequency distributions of tuffs and clastics show such strong differences that they can be characterized by standardized distributions. By comparing the shape frequency distributions of mixed sediment samples, it is possible to determine the relative contribution of tuff and clastics to any sediment sample taken within the drainage network. The Piapi Canyon, Indian Trail, and Eleana Formations have produced the thick alluvium sequence in the Rainier Mesa region of Yucca Flat. We believe it is likely that these grain shape relationships can also be applied to subsurface samples. Not only would this extended application enable more accurate correlation of alluvial layers, but more precise determination of the clastic-tuff contact within the alluvium sequence might also be possible.

First order leveling to be conducted as part of an environmental monitoring program for a geopressured test well was reported. 39.43 kilometers of first order levels were run to NGS specifications. Twelve Class B type bench marks were set to NGS specifications. The adjusted elevation of bench mark C-1209 was used as a starting elevation and is based on a supplementary adjustment of April 6, 1979 by NGS. The closure for the loop around the well site is -0.65 millimeters. The distance around the loop is 1.29 kilometers, the allowable error of closure was 4.54 millimeters. The initial leveling of this well was performed in 1977. A thorough search for their monumentation was conducted. No monuments were found due to the lack of adequate monument descriptions. Therefore, an elevation comparison summary for this report is only available along the NGS lines outside the well area. The first order level tie to line No. 101 (BMA-1208) was +3.37 millimeters in 17.21 kilometers. The allowable error of closure was 12.44 millimeters.

The Nevada TestSite–Directed Research and Development (SDRD) program completed its fifth successful year of research and development activities in FY 2006. Forty new projects were selected for funding this year, and ten FY 2005 projects were brought to conclusion. The total funds expended by the SDRD program were $6 million, for an average per-project cost of $120 thousand. Beginning in May, 2006 programmatic burden rates were applied to SDRD project costs. An external audit conducted in September 2006 verified that appropriate accounting practices were applied to the SDRD program. Highlights for the year included: the filing of 27 invention disclosures for intellectual property generated by FY 2006 projects; programmatic adoption of four FY 2005 SDRD-developed technologies; participation in the tri-Lab Laboratory Directed Research and Development (LDRD) and SDRD program review that was broadly attended by NTS, NNSA, LDRD, and U.S. Department of Homeland Security representatives; peer reviews of all FY 2006 projects; and the successful completion of 50 R&D projects, as presented in this report.

Experiments are needed to locate phase boundaries and to provide both Hugoniot data and off-Hugoniot data (such as principle isentrope, refreezing, dynamic strength, etc.) achieved through complex loading paths. The objective of the current work was to de- velop a large bore (3.5 inch or greater) powder gun capable of accelerating projectiles to moderately high velocities exceeding 2 km/s for impact experiments. A total of 24 ex- periments were performed to measure the projectile velocity, breech strain, and projectile tilt to demonstrate the performance of the gun up to the maximum breech capacity of 16 pounds of propellant. Physics experiments using a multislug method were performed to obtain sound speed and Hugoniot for shocked cerium metal and to demonstrate the ability of the large bore gun to conduct well-defined, plate-impact experiments. In addition, six experiments were performed on the prototype containment system to examine the ability of the launcher and containment system to withstand the impact event and contain the propellant gases and impact debris postshot. The data presented here were essential for qualification of the launcher for experiments to be conducted at the U1a complex of the Nevada TestSite.

This Closure Report (CR) presents information supporting a closure recommendation for Corrective Action Unit (CAU) 394: Areas 12, 18, and 29 Spill/Release Sites, Nevada TestSite, Nevada, in compliance with the requirements of the Federal Facility Agreement and Consent Order. This CAU contains six Corrective Action Sites (CASs): 12-25-04, UST 12-16-2 Waste Oil Release; 18-25-01, 18-25-02, 18-25-03, Oil Spills; 18-25-04, Spill (Diesel Fuel); and 29-44-01, Fuel Spill, located within Areas 12, 18, and 29 on the Nevada TestSite. The purpose of this CR is to provide documentation supporting recommendations of no further action or closure in place for CASs within CAU 394. Throughout late 2002 and early to mid 2003, closure activities were performed as set forth in the CAU 394 Streamlined Approach for Environmental Restoration Plan. The closure activities identified the nature and extent of contaminants of potential concern at the CASs, and provided sufficient information and data to complete appropriate corrective actions for the CASs. Soil in CASs 18-25-02 and 18-25-03 containing polychlorinated biphenyls exceeding the action levels established by the Nevada Administrative Code were removed for proper disposal. The soil remaining in these CASs containing petroleum hydrocarbons exceeding the action level were closed in place with use restrictions. Corrective Action Sites 18-25-04 required no further corrective action; closure in place is required at CASs 12-25-04, 18-25-01, 18-25-02, 18-25-03, and 29-44-01; and use restrictions are required at CASs 12-25-04, 18-25-01, 18-25-02, 18-25-03 and 29-44-01. In summary, no corrective action plan is required for CAU 394.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office